BEGIN:VCALENDAR
VERSION:2.0
PRODID:-//CERN//INDICO//EN
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Chemical dosimetry for BNCT mixed radiation fiel
 d and conformal radiotherapy
DTSTART;VALUE=DATE-TIME:20120921T062000Z
DTEND;VALUE=DATE-TIME:20120921T064000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-216@cern.ch
DESCRIPTION:Speakers: Prof. GAMBARINI\, Grazia (Università degli Studi di
  Milano\, Italy)\nGel dosimeters allow in-phantom verification of the abso
 rbed dose spatial distribution in conformal radiotherapy treatments. Parti
 cularly advantageous are Fricke gel dosimeters in form of layers that can 
 be analysed with very simple instrumentation\, give precise results if pro
 perly calibrated and offer particular advantages in the mixed neutron-gamm
 a fields of boron neutron capture therapy (BNCT).\nFricke gel layer dosime
 ters are based on ferrous sulphate solution (Fricke solution) containing X
 ylenol-Orange\, infused in 3mm-thick gel matrix. The measurable effect pro
 duced by ionising radiation is a change in the wavelength of visible light
  absorbance. The dosimeters are imaged with a CCD camera system before and
  after irradiation\, and the measured difference of optical density around
  585nm wavelength is proportional to the absorbed dose. The good tissue eq
 uivalence of such dosimeters\, consisting in a dilute water solution\, and
  the independence of their response on photon energy in the range of inter
 est for radiotherapy\, constitute valuable characteristics for appropriate
  in-phantom dosimetry in conformal radiotherapy.  Moreover\, the layer geo
 metry has allowed the development of a calibration procedure that enable a
 chieving very high precision (within 3%).\nThe layer geometry of such gel 
 detectors is particularly convenient also in BNCT dosimetry.  In fact\, a 
 method for imaging the various dose components has been proposed and widel
 y applied\, based on couples of gel-dosimeters having a suitable differenc
 e in their isotopic composition.  Thanks to layer geometry\, neutron trans
 port is not sensibly affected by such a gel matrix variation because it is
  mainly determined by the tissue-equivalent phantom around dosimeters. The
 refore\, it is possible to measure the spatial distribution of the dose du
 e to the charged particles generated by B-10 reactions with thermal neutro
 ns\, of the gamma dose due to background and to photons emitted in the rea
 ctions of thermal neutrons with hydrogen and also of the dose due to the f
 ast component of the epithermal neutron beam.\n\nhttp://indico.cern.ch/con
 tributionDisplay.py?contribId=216&sessionId=30&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=216&sessionId=3
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Radiosynthesis of 18F-Labeled Diclofenac Hydroxy-Derivative as pot
 ential micro-PET imaging tracer
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-217@cern.ch
DESCRIPTION:Speakers: LIN\, Manjing (Singapore Health Services Pte Ltd\, C
 hina)\nMethods and Materials: \nThe diclofenac hydroxy-derivative precurso
 r was prepared via five steps synthesis from 2\,6-dichloroaniline.\nThe ra
 dio-synthesis was carried out according to the method described by Wang MW
  et al  with some modifications. It started from the displacement of tosyl
  group from 1\,2-bistosyoloxyethane with 18F-fluoride to afford 18F-fluoro
 ethyltosylate followed by fluoroethylation of diclofenac hydroxy-derivativ
 e precursor. Both one-pot and two pot methods were studied. Purification o
 f intermediate and final product was carried out with Sep-pak silica cartr
 idge eluting with diethyl ether and dichloromethane respectively.\nThe ana
 lyses of the labeled intermediate 18F-fluoroethyl tosylate and the final p
 roduct 10-18F-fluorethyloxy diclofenac and its reference compounds were ca
 rried out with TLC. The plates were developed with Dichloromethane/methano
 l (V:V 95/5) solution. The radioactivity on the plates was detected by Rad
 io-TLC Scanner. No HPLC system was needed for the purification of the prod
 uct.\n    \nResults: 18F- Fluorethyloxy diclofenac was prepared via indire
 ct labeling consisting of fluorination of 1\,2-bis(tosyloxy)ethane and flu
 oroethylation of diclofenac hydroxy-derivative. The radiochemical yield at
  the end of two steps was about 87%. \n\nConclusion: In conclusion\, an ef
 ficient and convenient chemical and radiochemical synthesis of the referen
 ce standards and target tracer\, 18F labeled small molecule 18F- Fluorethy
 loxy diclofenac as a new PET imaging tracer\, have been well developed. Th
 e overall radiosynthesis yield of the tracer was 87%.\n\nhttp://indico.cer
 n.ch/contributionDisplay.py?contribId=217&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=217&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:A new PTS for short-time neutron activation analysis
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-214@cern.ch
DESCRIPTION:Speakers: Prof. ISMAIL\, Saleh (Atomic Institute-Vienna\, Aust
 ria)\nA fully-automatic pneumatic transfer system (PTS) for short-time neu
 tron activation analysis (STNAA) is constructed to utilize two irradiation
  positions of a TRIGA Mark-II research reactor. The system consists of a v
 ertical in-core irradiation terminal and a terminal for a radial radiation
  beam tube. Both terminals were constructed for a sample capsule of 3.5 ml
 . The transfer time of the irradiated capsule (4g) for a distance of 30 me
 ters is found to be less than 3 seconds using pressurized air (3 bars). Th
 e Irradiation position of the sample capsule inside the beam tube is set a
 t an angle of 45o and can be equipped with a moveable Cd filter for therma
 l/epithermal irradiations. The system is equipped with two sample changers
  for automatic analysis of un-irradiated and pre-irradiated samples for th
 eir short- or long-lived nuclides. A software package for the system is de
 veloped using two different codes. The first is based on PLC-code to contr
 ol the irradiation procedures while the second is based on a Delphi to man
 age the measuring procedures with one of two digital spectrometers (Genie 
 and Dspec). The software package manages the complete analysis procedure f
 or reliable hardware/software control of the pneumatic- and the counting s
 ystems. The counting chamber is fabricated from Plexiglas and equipped wit
 h a linear motor to set the sample automatically at one of 4 geometry-posi
 tions\, according to the activity of the analyzed sample.\n\nhttp://indico
 .cern.ch/contributionDisplay.py?contribId=214&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=214&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Gamma external radiation dose for Mexican population
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-215@cern.ch
DESCRIPTION:Speakers: Dr. NAVARRETE\, Manuel (National University of Mexic
 o\, Mexico)\nSince 1992 the Chemistry Faculty of the National University o
 f Mexico has been performed studies about environmental natural radioactiv
 ity\, gamma\, radon and thoron levels in the Metropolitan Zone of Mexico C
 ity (MZMC) and other cities like the Metropolitan Zone of Guadalajara (MZG
 ). This work report the gamma absorbed dose rate   measured at the beginni
 ng  with Ca SO4: Dy + PTFE and in the  last studies with a LiF\; Mg\, Cu\,
  P+PTFE thermoluminiscent dosimeters developed at the National Institute o
 f Nuclear Research\, ININ. This dosimeter fulfills the ANSI-N-545 code for
  environmental monitoring. Each  dosimetric-plastic package  contains two 
  pellets\,  that  were  placed  at  1.50  to  2  m  above the floor at ind
 oor dwellings and  exposed.  The total sampling period was one year divide
 d in four periods of three months each one.  TLD’s were evaluated in a H
 arshaw analyzer Model 4000 coupled to a PC. Mean arithmetic value of gamma
  absorbed dose rate at indoor air in the MZG dwellings (not-subtracted cos
 mic background) was 0.12 μGy.h–1 as mean with fluctuations from 0.07 to
  0.15 μGy.h–1. The arithmetic mean value is higher than that obtained i
 n the Metropolitan Zone of Mexico City\, in spite that the MZG altitude is
  lesser than the first one\; % RMD average precision for duplicate pairs o
 f gamma exposure rate was lower than 5%. Taking into account the conversio
 n factor of 0.7 Sv.Gy–1 for gamma-rays and an indoor occupancy factor of
  80%  the annual effective equivalent dose was calculated and compared to 
 the to the world average.\n\nhttp://indico.cern.ch/contributionDisplay.py?
 contribId=215&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=215&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Sorption of niobium on Olkiluoto soil samples
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-212@cern.ch
DESCRIPTION:Speakers: SÖDERLUND\, Mervi (University of Helsinki\, Finland
 )\nA KBS-3-type repository for the spent fuel from the Finnish nuclear pow
 er reactors in Olkiluoto and Loviisa is to be built in the bedrock at the 
 Olkiluoto site at the depth of approximately 400 m. The final disposal pla
 n includes a safety assessment of the spent nuclear fuel\, where the poten
 tial dose contributing nuclear waste nuclides for man are specified. As a 
 part of this assessment\, the transport of these prioritized radionuclides
  from the geosphere to surface environment and their fate within is modell
 ed and evaluated. Nb-94 is classified as high priority radionuclide in the
  long-term safety assessment of spent nuclear fuel. \n\nThe retention of n
 iobium was studied on Olkiluoto soil samples representing humus layer and 
 mineral soil layers. Sampling extended from the soil surface to the bedroc
 k surface. Soil samples were used without pretreatment\, e.g. drying or si
 eving. Mass distribution coefficient\, Kd\, describing the effectiveness o
 f the retention was determined by batch sorption tests. The liquid phase u
 sed in the tests was synthetic soil solution simulant\, which composition 
 is similar to the composition of Olkiluoto soil solution. The equilibrium 
 time ranged from one day to three weeks for humus samples and from one wee
 k to nine weeks for mineral soil samples. The final activity of the Nb-95 
 tracer was determined by gammaspectrometry with Wizard ™ 3’’. \n\nTh
 e sorption of niobium was found to be high on mineral soil samples as the 
 Kd values ranged between 1.1x10^3 ml/g and 1.0x10^6 ml/g. Niobium was reta
 ined on colloidal particles which was seen as an increase in the Kd values
  upon filtering. Sorption showed no clear dependence on time or sample dep
 th. The sorption on humus samples was smaller as the Kd values ranged from
  230 ml/g to 1.2x10^3 ml/g.\n\nhttp://indico.cern.ch/contributionDisplay.p
 y?contribId=212&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=212&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Environmental impact due to the operation of a tin and lead indust
 ry inferred by lichens
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-213@cern.ch
DESCRIPTION:Speakers: Dr. LEONARDO\, Lucio (Ipen/CNEN\, UNIP- Universidade
  Paulista\, Brasil)\nFor the last 20 years\, the brazilian most important 
 tin and lead industry has been producing these metals in Pirapora do Bom J
 esus\, a city placed in state of Sao Paulo. As a consequence of the indust
 rial process\, wastes are released into the environment mainly as dust and
  in slag which is stored in piles in open air. The concentration of natura
 l radioactivity can be increased as well as the trace elements by the indu
 strial process. This paper analyzed the environmental impact due to the op
 eration of a tin and lead industry using lichens as bioindicator. The lich
 en specie chosen was Canoparmelia texana because it is one of the most wid
 ely spread in natural ecosystem and also in polluted urban areas. Samples 
 of these specie and soil were collected around the industry and the concen
 trations of the natural radionuclides from 238U and 232Th series\, trace e
 lements and lead isotopic ratio were determined using the techniques neutr
 on activation analysis (NAA)\, alpha and gamma spectrometry\, gross alpha 
 and beta counting and thermal ionization mass spectrometer (TIMS)\, respec
 tively. The lichen samples collected closer to the industry presented the 
 highest concentrations of 238U\, 226Ra\, 210Pb\, 232Th\, 228Ra\, Hf and Ta
  and\, by the results of lead isotopic ratio\, it was possible verifies th
 e fingerprint of the contamination conforming the efficiency of lichens as
  bioindicator in environmental studies.\n\nhttp://indico.cern.ch/contribut
 ionDisplay.py?contribId=213&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=213&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Decomposition of boric acid solutions and evol
 ution of gases under mixed thermal and fast neutrons and gamma radiation
DTSTART;VALUE=DATE-TIME:20120918T165500Z
DTEND;VALUE=DATE-TIME:20120918T171000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-210@cern.ch
DESCRIPTION:Speakers: Dr. IM\, Hee-Jung (Nuclear Chemistry Research Divisi
 on\, Korea Atomic Energy Research Institute\, Korea)\nUsually radiolytic g
 ases (such as oxygen and hydrogen molecules) are not detected in cooling s
 ystem of a research reactor even under room-temperature irradiation condit
 ions. However\, the presence of certain amounts of boric acid\, which is k
 nown as a water soluble thermal neutron absorber\, produces an evolution o
 f gases in significant quantity in the reactor at room temperature. To stu
 dy the radiolysis of the cooling water\, we irradiated several water sampl
 es containing natural\, 10B-enriched\, and mixed boric acid in the ranges 
 of 0 to 2000 ppm for the function of 10B concentration. \nThe boric acid c
 oncentration increased the extent of water decomposition compared to the a
 bsence of boric acid because of the nuclear effect from 10B(n\,α)7Li\, wh
 ich is due to the radiation issued from a 10B reaction with thermal neutro
 ns. It is well known that the products of water radiolysis are molecular (
 H2\, O2\, H2O2) and radical (H\, OH\, e-aq\, HO2) species\, and that high 
 linear energy transfer (LET) radiation of 10B(n\,α)7Li produces more mole
 cular species than radical ones. The high LET radiation of alpha rays\, pr
 oduced from the addition of boric acid in water\, inhibits the recombinati
 on mechanisms of radicals and stops the chain reaction.\nThe radiolysis of
  a boric acid solution under mixed thermal and fast neutrons and gamma rad
 iation was examined quantitatively and qualitatively using a inductively c
 oupled plasma mass (ICP-MS) spectrometer for measuring the 10B and 11B con
 centration ratio\; a flameless atomic absorption (AA) spectrometer for the
  concentration of a product\, 7Li\,\; a gas mass (Gas-MS) spectrometer for
  the measurement of H2\, O2\, and H2O concentrations\; and titration metho
 ds for the H2O2 concentration. The total amounts of produced gases will be
  discussed with a comparison of the theoretical calculation values.\n\nhtt
 p://indico.cern.ch/contributionDisplay.py?contribId=210&sessionId=22&confI
 d=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=210&sessionId=2
 2&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Characteristics of Uranium species when U(III) in a LiCl-KCl molte
 n salt was leached out with water and ionic liquid
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-211@cern.ch
DESCRIPTION:Speakers: Dr. IM\, Hee-Jung (Nuclear Chemistry Research Divisi
 on\, Korea Atomic Energy Research Institute\, Korea)\nAs a type of spent n
 uclear fuel treatment\, the pyrochemical process is well known for its non
 -proliferation of nuclear fuel cycles\, separation of long-term radioactiv
 e nuclides during processing\, the recovery of uranium for re-use as a nuc
 lear fuel\, and a significant volume-reduction of high-level wastes. After
  the complete pyrochemical processing is finished\, a remaining small amou
 nt of salt waste\, apart from the salt for recycling purposes\, will be st
 ored for the long term and is composed of some actinides and lanthanide sp
 ecies (mainly exist as 3+ ions) dissolved in molten salt. In this study\, 
 we investigated the behavior of U(III) dissolved in LiCl-KCl molten salt\,
  when U(III) was leached out with water compared to ionic liquid\, to obta
 in better understandable information for long-term waste salt storage.\nA 
 U(III) in LiCl-KCl eutectic salt was prepared from the reaction of uranium
  metal with cadmium chloride in a LiCl-KCl mixture (44 wt.% LiCl) at 450 o
 C in an Ar-atmosphere glove box. For a characteristic study of U(III) unde
 r stable and unstable conditions\, the U(III) in the LiCl-KCl eutectic sal
 t was first dissolved in an appropriate ionic liquid and water. \nU(III) i
 s unstable (oxidized) in alkali fluoride molten salt or under general cond
 itions but is stable in LiCl-KCl molten salt. Moreover\, the ionic liquid 
 (1-hexyl-3-methyl-imidazolium chloride) used in this research did not caus
 e an oxidation or reduction of U(III) like water does. The behavior of U(I
 II) in LiCl-KCl is dependent on the contacted solvent (ionic liquid or wat
 er)\, and the results\, including the actual assignment of each peak of th
 e spectroscopic spectra\, were conclusive.\n\nhttp://indico.cern.ch/contri
 butionDisplay.py?contribId=211&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=211&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Nuclear energy chemistry and recent progresses i
 n nuclear fuel reprocessing in China
DTSTART;VALUE=DATE-TIME:20120918T133000Z
DTEND;VALUE=DATE-TIME:20120918T135000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-165@cern.ch
DESCRIPTION:Speakers: Dr. SHI\, Wei-Qun (Institute of High Energy Physics\
 ,Chinese Academy of Sciences\, China)\nNuclear energy chemistry is one of 
 the frontier areas of chemistry with high impact on national security\, en
 ergy supply\, scientific advances\, social and economic development. Nucle
 ar energy chemistry in China is now experiencing a renaissance\, which is 
 being strongly motivated by China’s huge demand for nuclear energy. In t
 his presentation\, the progress in nuclear energy chemistry of China is se
 lectively addressed. Some hot topics have been summarized and the main res
 earch results achieved by Chinese scientists in this field are highlighted
 \, with emphasis on the chemistry of nuclear fuel cycle\, such as front-en
 d chemistry\, materials chemistry and nuclear fuel fabrication\, actinide 
 chemistry and nuclear fuel reprocessing as well as nuclear waste disposal.
  Some measures about how to promote the radiochemical education and resear
 ch in China are suggested\, and future perspectives are briefly outlined a
 s well.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=165&sess
 ionId=19&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=165&sessionId=1
 9&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Studies of Trace Element Species in Macromolecul
 es and Protein Nanoclusters by Nuclear and X-Ray Techniques
DTSTART;VALUE=DATE-TIME:20120920T072000Z
DTEND;VALUE=DATE-TIME:20120920T074000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-218@cern.ch
DESCRIPTION:Speakers: Prof. CHATT\, A. (Dalhousie University\, Canada)\nTr
 ace elements play an important role in biological activities of living mat
 ter. A considerable amount of data on the total trace element levels in va
 rious biological tissues already exists in the literature. However\, trace
  elements are mainly incorporated in proteins in these systems. It is impo
 rtant to separate these protein-bound trace elements for the identificatio
 n as well as characterization of the chemical species in order to develop 
 a mechanism and an understanding of their biological activities. We have u
 sed analytical and bioanalytical techniques such as dialysis\, pH variatio
 n\, ammonium sulphate precipitation\, chromatofocusing\, isoelectrofocusin
 g and isotachophoresis\, ion-exchange\, hydroxyl apatite\, size-exclusion\
 , gas and liquid chromatography complemented by NAA\, MS\, and NMR to stud
 y macro-molecular species of As\, Br\, Ca\, Cl\, Cu\, Fe\, I\, K\, Mg\, Mn
 \, Mo\, Na\, Rb\, S\, Se\, V\, and Zn in bovine kidneys. Lately we are int
 erested in a better understanding of the interaction of metal nanoparticle
 s (NPs) with proteins through speciation analysis. Because of the size\, s
 ome metal NPs can have significant effects on their quantum electronic and
  chemical properties. We are studying bio-functionalization of Au\, Ag and
  a few other metal NPs on surfaces such as Ti that can be used for more ef
 ficient drug delivery and implant surface modification using SEM and eleme
 nt-specific X-ray techniques such as EXAFS\, XANES and XPS.\n\nhttp://indi
 co.cern.ch/contributionDisplay.py?contribId=218&sessionId=27&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=218&sessionId=2
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Uranium in ground water samples from Anthemountas Basin\, Northern
  Greece
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-219@cern.ch
DESCRIPTION:Speakers: Prof. IOANNIDOU\, Alexandra (ARISTOTLE UNIVERSITY OF
  THESSALONIKI\, Greece)\nThe activity concentrations of 238U and 234U have
  been determined in groundwater samples of deep wells in Anthemountas rive
 r basin\, Northern Greece. The analysis was performed by alpha spectroscop
 y after pre-concentration and separation of uranium by cation exchange and
  finally its electro-deposition on stainless steel discs. Analysis by gamm
 a spectroscopy was also performed. The uranium concentrations in the regio
 n of study and during winter period varied strongly between 9 and 42.6 ppb
 . These variations in concentrations of uranium are correlated with the di
 fferent geological formations and water flow paths in the study area. In t
 he case of Anthemountas river basin the available data revealed a very com
 plex system of aquifers with significant extent in both lateral and vertic
 al sense. The study area is covered with sediments deposits consisting of:
  i) Valley deposits: sandy clay\, ii) Lower terrace system: gravels and sa
 nd under a clayey cover\, iii) Upper terrace system: grits and pebbles wit
 h loam or sandy clay\, iv) Fans of different age\, v) Red clay series: red
  to brick red\, silty clays with mica and calcareous concretionary bodies\
 , while the area to the north and south are covered by vi) Limestones recr
 ystallised\, Granodiorite\, viii) Gabbro and ix) Dunites and peridotites. 
 The hydrogeology varies significantly for the area of interest due to the 
 anisotropy of the sediments of the basin. Their behaviour is driven mainly
  by their primary porosity and the secondary porosity caused from the faul
 ting tectonics making it easier for water flow in certain areas. From the 
 radiological point of view\, using ground waters for human consumption wou
 ld result in significantly increased radiation doses and their utilization
  for irrigation purposes would imply an excessive radiation exposure to po
 pulation\, in cases of high uranium concentrations.\n\nhttp://indico.cern.
 ch/contributionDisplay.py?contribId=219&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=219&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Cyclotron produced <sup>45</sup>Ti – production\, purification a
 nd yields
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-133@cern.ch
DESCRIPTION:Speakers: Dr. FRANKE\, Karsten (Dept. Reactive Transport\, Ins
 titute of Resource Ecology\, Helmholtz-Zentrum Dresden-Rossendorf\, Leipzi
 g-Site\, Germany \; Dept. Neuroradiopharmaceuticals\, Institute of Radioph
 armacy\, Helmholtz-Zentrum Dresden-Rossendorf\, Leipzig-Site\, Germany)\nS
 tudies of the environmental fate of nanoparticulate TiO2 require suitable 
 tools for tracing the nanoparticles in complex environments and media. A p
 romising method is the isotopic radiolabelling of the TiO2-nanoparticles w
 ith 44Ti (T1/2 = 47.3 a) or 45Ti (T1/2 = 3.08 h). Due to the different dec
 ay modes and half-lives\, different experimental setups are accessible wit
 h these radioisotopes. The presented work is focused on the production and
  purification of the short –lived positron-emitting radionuclide 45Ti (n
 .c.a.). \nFor this purpose\, we used the nuclear reaction 45Sc(p\,n)45Ti [
 1]. The irradiation was done at a COSTIS target station mounted at a 2 m b
 eam transfer line of a Cyclone® 18/9 (IBA molecular). The mono-isotopic n
 atural scandium allowed an easy target design. A scandium foil (thickness:
  100 µm) was put together with an energy-degrading foil into a disk-like 
 sample holder and was then transferred into the COSTIS target station. The
  irradiation was carried out with 12 MeV protons and a current of 20 µA f
 or 20 min – 30 min.\nRadionuclide separation and purification was done b
 y means of ion exchange chromatography [2] or liquid-liquid extraction [3]
 . Both methods were compared. Higher yields and better purification result
 s were obtained with liquid-liquid extraction. The yield of the liquid-liq
 uid extraction was about 75 % - 80 %\, n.c.a. 45Ti stock solution (1 M HCl
 ) had a activity concentration of up to 120 MBq/mL.\n\nReferences\n[1] McG
 ee T\, Rao CL\, Saha GB\, Yaffe L (1970) Nucl Phys A150:11-29.\n[2] Vâver
 e AL\, Laforest R\, Welch MJ (2005) Nucl Med Biol 32:117-122.\n[3] Sevasti
 nov YG (1974) J Radioanal Chem 21:247-257.\n\nhttp://indico.cern.ch/contri
 butionDisplay.py?contribId=133&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=133&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Detection of irradiated foods using TL\, ESR and GC/MS
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-132@cern.ch
DESCRIPTION:Speakers: Mrs. KANG\, Yoonjung (Busan Regional Korea Food & Dr
 ug Administration\, Korea)\nFood irradiation technique is extremely effect
 ive at reducing food-borne illness as well as losses caused by pathogenic 
 microorganisms. However\, there is a need to detect the use of food irradi
 ation to ensure that food is labeled correctly. In present\, several metho
 ds are available to detect irradiated food. Among them\, thermoluminescenc
 e(TL)\, electron spin resonance(ESR) and gas chromatography/mass spectrome
 try(GC/MS) detection are the leading techniques. The aim of this study is 
 to set up applicability for foods which are not allowed to be irradiated i
 n Korea. The groups of dried fruits and seeds were collected. The results 
 showed that it is possible to apply TL method to all foods with mineral. I
 n ESR method\, food containing sugar showed radiation-induced crystalline 
 sugar radicals\, but the others did not exhibit radiation-induced radicals
 . In case of seeds\, GC/MS method was applied and radiation-induced hydroc
 arbons were observed. According to the conclusion based on our experimenta
 l results\, TL\, ESR and GC/MS methods were successfully applied to examin
 e irradiated and non-irradiated foods.\n\nhttp://indico.cern.ch/contributi
 onDisplay.py?contribId=132&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=132&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Determination of Mineral Contents in Korean Domestic Unpolished Ri
 ce and Bean Samples by Neutron Activation Analysis
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-131@cern.ch
DESCRIPTION:Speakers: Mr. MOON\, JongHwa (Korea Atomic Energy Research Ins
 titute\, Korea)\nAs scientists have focused their researches on the health
  impacts caused by mineral nutrient deficiencies and hazardous elements\, 
 public concern regarding mineral intake from dietary food is rising. For t
 his reason\, the dietary habit of Koreans has shifted from white rice to m
 ore nutritious rice like unpolished rice and rice mixed with beans. The ob
 jectives of this study were to determine the mineral contents in unpolishe
 d rice and bean samples and to compare the level of mineral contents betwe
 en the analyzed samples. Four kinds of unpolished rice and three kinds of 
 beans were chosen as the target samples and seventeen mineral contents\, A
 l\, As\, Br\, Ca\, Cl\, Co\, Cr\, Cs\, Cu\, Fe\, K\, Mg\, Mn\, Na\, Rb\, S
 e\, and Zn were determined by a neutron activation analysis. K shows the h
 ighest values among the analyzed elements from unpolished rice and bean sa
 mples. Only As in the unpolished rice samples shows higher contents than t
 hat in the bean samples. Ca\, Cu\, Fe and K in the unpolished rice are 8-t
 imes higher than those in the beans. Mg and Zn in the unpolished rice are 
 slightly higher than those in the beans. Additionally\, these results were
  compared with mineral contents in white rice\n\nhttp://indico.cern.ch/con
 tributionDisplay.py?contribId=131&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=131&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:On the way to the synthesis of the first transactinide carbonyl co
 mplex
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-130@cern.ch
DESCRIPTION:Speakers: Dr. EVEN\, Julia (Helmholtz Institut Mainz\, Germany
 )\nUntil now gas phase chemical studies of transactinides (TANs) focused o
 n simple\, inorganic compounds. The harsh conditions behind the target (pl
 asma and heat) in general prevented direct synthesis of\, e.g.\, organomet
 allic compounds. In the last years\, this limitation could be overcome by 
 the combination of a physical recoil separator with chemistry setups. [1] 
 \nWe report here on initial experiments with this technique that focused o
 n metal-carbonyl complexes. Seaborgium hexacarbonyl has been predicted to 
 be stable. [2] The pi-back bonding\, characteristic for the metal-carbon b
 ond in carbonyls\, should be stronger than in the complexes formed with th
 e lighter homologues due to the relativistic expansion of the d-orbitals.[
 2] On the way to experiments with Sg\,  studies of its lighter homologues 
 were performed. Suitable isotopes of Mo were produced in neutron-induced f
 ission of Cf-249 at the TRIGA reactor Mainz. “Hot” recoil atoms formed
  volatile complexes upon thermalization in a CO containing atmosphere. The
  complexes could be rapidly transported in the gas stream to counting or g
 as chromatography setups. [3] At the UNILAC accelerator at GSI\, the gas-f
 illed recoil separator TASCA [4] was used to study the synthesis and chemi
 cal properties of tungsten and osmium carbonyl complexes\, using condition
 s directly applicable in a TAN experiment. [3]\nThis new chemical system p
 romises to give access to a new TAN compound class. Furthermore\, it could
  be used to provide clean of\, e.g.\, Sg isotopes with half-lives of at le
 ast a few seconds for nuclear reaction and nuclear structure studies. Eluc
 idation of the experimentally found\, but theoretically unexplained isomer
 ic state in Sg-265 [5\,6]  will be the goal of first experiments.	\n	\n[1]
    Ch. E. Düllmann et al.\, Nucl. Instr. Meth. A 2005\, 551\, 528–539.\
 n[2]    C. S. Nash\, B. E. Bursten\, J. Am. Chem. Soc. 1999\,121\, 10830-1
 0831.\n[3] 	J. Even\, et al.\, Inorg.Chem. 2012\, 51\, 6431-6422.\n[4]	A. 
 Semchenkov et al.\, Nucl. Instr. Meth. B.2008\, 266\, 4153-4161.\n[5]	Ch.E
 . Düllmann\, A. Türler Phys. Rev. C 2008\, 77\, 64320.\n[6]	H.Haba et al
 \, Phys Rev. C 2012\, 85\, 024611.\n\nhttp://indico.cern.ch/contributionDi
 splay.py?contribId=130&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=130&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Selectivity of bis-triazinyl bipyridine ligand
 s for americium(III) in Am/Eu separation by solvent extraction. Quantum me
 chanical study
DTSTART;VALUE=DATE-TIME:20120918T164000Z
DTEND;VALUE=DATE-TIME:20120918T165500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-137@cern.ch
DESCRIPTION:Speakers: Prof. NARBUTT\, Jerzy (Institute of Nuclear Chemistr
 y and Technology\, Warsaw\, Poland)\nSelective separation of actinide elem
 ents from highly radioactive nuclear waste is the key issue for modern tec
 hnologies of nuclear waste reprocessing. Partitioning of long-lived minor 
 actinides\, in particular americium\, and their subsequent transmutation i
 nto short-lived radionuclides would lead to a significant reduction of lon
 g-term environmental hazard from this radiotoxic waste\, and contribute to
  the development of safe nuclear power. Derivatives of 6\,6’-bis([1\,2\,
 4]-triazin-3-yl)-2\,2’-bipyridine (BTBP)\, tetra-N-dentate lipophilic li
 gands which selectively extract trivalent actinides (An) over lanthanide f
 ission products (Ln) from nitric acid solutions to organic solvents (SANEX
  process)\, have been considered the most promising species for hydrometal
 lurgical recovering (partitioning) the minor actinides from high-level rad
 ioactive waste. \nTheoretical studies were carried out on two pairs of ame
 ricium and europium complexes formed by the BTBP ligands\, neutral [ML(NO3
 )3] and cationic [ML2]3+ where M = Am(III) or Eu(III)\, and L = 6\,6’-bi
 s-(5\,6-diethyl-1\,2\,4-triazin-3-yl)-2\,2’-bipyridine (C2-BTBP). Molecu
 lar structures of the complexes have been optimised and total energies of 
 the complexes in various media calculated using the DFT method (Gaussian 0
 9). Selectivity in solvent extraction separation of two metal ions is a co
 -operative function of contributions from all extractable metal complexes.
  The individual contributions depend on physico-chemical properties of the
  complexes and on their relative amounts in the system. Semi-quantitative 
 analysis of BTBP selectivity in the Am/Eu separation process has been carr
 ied out\, based on the contributions from the two pairs of Am(III) and Eu(
 III) complexes. To calculate the energy of Am/Eu separation\, a model of e
 xtraction process was used\, consisting of complex formation in water and 
 transfer of the formed complex to the organic phase. The greater thermodyn
 amic stability (in water) of the Am-BTBP complexes\, as compared with the 
 analogous Eu species\, caused by greater covalencies of the Am–N than Eu
 –N bonds\, is most likely the main reason of BTBP selectivity in the sep
 aration of the two metal ions. The other potential reason\, i.e. differenc
 es in lipophilic properties of the analogous complexes of Am and Eu\, is l
 ess important with regards to this selectivity.\nAnalysis of Am–BTBP and
  Eu–BTBP bonding in the complexes studied\, performed with the use of th
 eoretical methods: QTAIM\, CMO and NBO\, allows us to conclude that the or
 igin of the selectivity of BTBP ligands for Am over Eu is due to different
  contributions into bonding from various atomic orbitals of the Am(III) an
 d Eu(III) ions.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=
 137&sessionId=22&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=137&sessionId=2
 2&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - <sup>44\,43</sup>Sc and <sup>47</sup>Sc as mat
 ched pair for theranostic approach to peptide receptor radionuclide therap
 y
DTSTART;VALUE=DATE-TIME:20120917T103000Z
DTEND;VALUE=DATE-TIME:20120917T104500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-136@cern.ch
DESCRIPTION:Speakers: Mr. KRAJEWSKI\, Seweryn (Institute of Nuclear Chemis
 try and Technology\, Dorodna Street 16\, 01312 Warsaw\, Poland)\nRecently\
 , great effort is put in development of personalised treatment\, including
  precise diagnoses and therapy using the same molecular targeting vectors.
  Scandium radioisotopes give opportunity to obtain PET/CT images using 44S
 c (τ1/2 = 3.92 h) and 43Sc (τ1/2 = 3.89 h) and to treat tumours with a l
 ow energy β--particles using 47Sc (τ1/2 = 3.35 d). The aim of our work w
 as to developed simple production procedures of those radionuclides and to
  compare 4xSc-DOTATATE labelling efficiency.\nHighly enriched 44CaCO3\, 47
 TiO2 and super pure natCaCO3 were used as a target materials. 44Sc was obt
 ained in 44Ca(p\,n)44Sc and 43Sc in 40Ca(α\,p)43Sc reaction in Joint Rese
 arch Centre (Ispra\, Italy)\, while 47Sc was produced in research reactor 
 “Maria” (Świerk\, Poland) in 47Ti(n\,p)47Sc reaction. CaCO3 targets w
 ere dissolved in HCl and an ion exchange resin Chelex 100 was used to sepa
 rate 44/43Sc from target material. The irradiated 47TiO2 was dissolved in 
 HFconc (80 oC). An anion exchange bed\, Dowex® 1X8\, was used to separate
  47Sc from 47Ti. For additional purification of 47Sc\, cation exchange col
 umn Dowex® 50WX4 was used. 4xSc-DOTATATE was synthesised with different a
 mounts of the peptide and in different pH.\n	The separation on the Chelex 
 100 and Dowex® 1X8 resins are efficient. We received high yield of DOTATA
 TE labelling with the three radionuclides. For 15 nmol of the bioconjugate
  the labelling yield exceed 99%. We checked also the possibility of peptid
 e labelling with 44Sc without target separation using C18 Sep-Pak® column
  for purification of the 44Sc-DOTATATE.\nThe three radionuclides can be pr
 oduced in amount of several GBq. The proposed production procedures are si
 mple and fast. The synthesis and purification procedure can be simplified 
 using C18 Sep-Pak® columns. The 44\,43Sc and 47Sc matched pair gives oppo
 rtunity to further development of peptide receptor radionuclide therapy.\n
 \nhttp://indico.cern.ch/contributionDisplay.py?contribId=136&sessionId=15&
 confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=136&sessionId=1
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Transmutation of minor actinides in the molten s
 alt reactor recently studied in Russia
DTSTART;VALUE=DATE-TIME:20120918T153000Z
DTEND;VALUE=DATE-TIME:20120918T155000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-134@cern.ch
DESCRIPTION:Speakers: Prof. PONOMAREV\, Leonid (NRC "Kurchatov Institute"\
 , Russia)\nL.I. Ponomarev\nNRC “Kurchatov Institute” and MUCATEX\, Mos
 cow\, Russia\n\nAbstract\n\nThe extremely high solubility of PuF3\, AmF3 a
 nd the fission product fluorides in the eutectics LiF-NaF-KF observed rece
 ntly (Fig.1 and 2) [1\,2] allows to create the efficient molten salt react
 or – transmuter (MSRT) for transmutation of the minor actinides (MA) fro
 m the spent nuclear fuel [3]. This observation opens also the way to the d
 evelopment of the molten salt fast reactor (MSFR) [2] with U-Pu cycle and 
 changes the general approach to its closed nuclear fuel cycle (CNFC) reali
 zation. The first results are presented\, obtained by the wide collaborati
 on of Russian Institutes in the framework of the Rosatom program “Strate
 gy of  the minor actinides transmutation in the closed nuclear fuel cycle
 ” [1]\, particularly the main parameters of the efficient subcritical MS
 RT which can transmute ~300 kg Am/GW•year without Pu consummation in the
  equilibrium mode operation [3].\n  \n1. Annual report #H.4F.45.90.11.1020
  “Optimization of the minor actinide reactor-transmuter characteristics 
 and its nuclear fuel cycle development”\, Rosatom\, 2011.\n2. A.M. Degty
 arev and L.I. Ponomarev\, “Fast molten salt reactor based on LiF-NaF-KF
 ”\, Atomnaya Energia\, 112\, p.367-368\, 2012.\n3. A.M. Degtyarev\, O.S.
  Feinberg\, F.I. Karmanov\, et. al.\, “Subcritical Molten Salt Reactor w
 ith fast/intermediate Spectrum for Minor Actinides Transmutation”\, Proc
 . GLOBAL-2011\, Murahari\, Japan\, paper 386820\, 2011.\n\nhttp://indico.c
 ern.ch/contributionDisplay.py?contribId=134&sessionId=22&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=134&sessionId=2
 2&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:The Effect of Cellulose Degradation Products on the Migration of 9
 0Sr in Cementitious Backfill using Radial Diffusion.
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-139@cern.ch
DESCRIPTION:Speakers: Mr. HINCHLIFF\, John ()\nMany concepts for the geolo
 gical disposal of intermediate level (ILW) and low level radioactive waste
  (LLW) include backfill materials based on admixtures of Ordinary Portland
  Cement (OPC). It is expected that these backfill materials will generate 
 high pH conditions and further\, the eventual corrosion of the metal canis
 ters used for disposal will promote a low Eh environment. It has been gene
 rally assumed that the safety functions of the cement within the near fiel
 d of a Geological Disposal Facility (GDF) will include reduction of the so
 lubility of many radionuclides and retardation of migration by sorption an
 d incorporation. \nDiffusion will remain the dominant migration mechanism 
 for radioisotopes throughout the post closure period. The radioisotope 90S
 r will be a significant component of the disposed waste and its half-life 
 of 28.8 years means that escape and migration from the GDF could be of sig
 nificance if it occurs within the operational phase or first few hundred y
 ears\, post closure. Cellulosic materials will also be disposed and previo
 us studies have shown that cellulose degradation products (CDP) produced a
 t high pH can enhance the migration of metal ions.\nThe radial diffusion e
 xperimental technique uses small pre-cast cylinders of the matrix under in
 vestigation. An appropriate concentration of 90Sr is introduced into a cav
 ity in the centre of the cylinder\, which is then sealed and placed in a s
 olution previously equilibrated with the matrix. The increase in concentra
 tion of the isotope in the external solution is then determined at defined
  time intervals. \nDiffusion experiments on NRVB (Nirex Reference Vault Ba
 ckfill) have been undertaken using 90Sr in the presence and absence of CDP
  or gluconate (a surrogate for the CDP mixture). The effect on the migrati
 on of 90Sr caused by addition of CDP is seen to be significant and work is
  currently underway to understand the mechanisms responsible.\n\nhttp://in
 dico.cern.ch/contributionDisplay.py?contribId=139&sessionId=26&confId=1834
 05
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=139&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Electrosynthesis of electrophilic n.c.a. 18F-fluorinating reagents
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-138@cern.ch
DESCRIPTION:Speakers: Mr. DRERUP\, Christian (Forschungszentrum Jülich Gm
 bH\, Germany)\nBecause of its extraordinary suitable decay properties fluo
 rine-18 is the most widely used radionuclide in positron emission tomograp
 hy (PET) [1]. Presently the radioorganic syntheses of no-carrier-added (n.
 c.a.) 18F-labelled products are practically limited to nucleophilic proced
 ures. This complicates or excludes n.c.a. syntheses of many putative trace
 r compounds and intensifies a special demand for electrophilic 18F-labelli
 ng. There is the unanswered question whether an electrochemical oxidation 
 of nucleophilic [18F]fluoride can lead to an electrophilic [18F]fluorine a
 nalogue. Since in organic fluorochemistry N-F compounds are known as highl
 y effective and selective electrophilic fluorinating agents [2]\, they wer
 e chosen to be synthesized with n.c.a. [18F]fluoride.\n\nBased on cyclic v
 oltammetric measurements an electrochemical synthesis of \n[18F]N-fluorobi
 s(phenylsulfonyl)amine was attempted. Bis(trifluoromethylsulfonyl)imide wi
 th 1-butyl-1-methylpyrrolidinium as counter anion was chosen as a putative
  suitable precursor. Due to its excellent physical and electrochemical pro
 perties this ionic liquid serves as conducting salt\, solvent and starting
  material at once and offers a simplified performance by avoiding major si
 de reactions. Cyclic voltammetry of bis(trifluoromethylsulfonyl)imide show
 ed two succeeding oxidation steps. The first step may lead to a resonance-
 stabilized radical before further oxidation causes the generation of an un
 stable cation and finally the decomposition of the compound.\n \nFurther e
 lectrosynthetic experiments were carried out in an established electrochem
 ical cell [3]. After intercalating [18F]fluoride from aqueous solution int
 o glassy carbon (Sigradur®G) the ionic liquid was added. At a tension of 
 6-8 V intercalated fluoride and bis(trifluoromethylsulfonyl)imide were exp
 ected to co-oxidize and recombine at the surface of the electrode. Product
 s were separated from their ionic contents and analyzed by radio-HPLC. An 
 unambiguous identification could not be achieved due to the lack of a refe
 rence compound. A resulting n.c.a. organic product\, however\, showed a si
 milar HPLC-retention with co-injected bis(phenylsulfonyl)imide as “pseud
 ostandard”. Thus\, in principle a production of an n.c.a. electrophilic 
 18F-fluorinating reagent starting from [18F]fluoride appears probable.\n\n
 References:\n\n[1] H. H. Coenen\, Fluorine-18 Labeling Methods in PET Chem
 istry\, The Driving Force in Molecular Imaging\, P. A. Schubiger\, L. Lehm
 ann\, M. Friebe (eds.)\, Springer Verlag 2007\, 16-50.\n\n[2] G. G. Furin\
 , A. A. Fainzilberg\, Russ. Chem. Rev.\, 68\, (1999)\, 653-684.\n\n[3] K. 
 Hamacher\, T. Hirschfelder\, H. H. Coenen\, Appl. Radiat. Isot.\, 56\, (20
 02)\, 519-523.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=1
 38&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=138&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Assessment of present and future radioactive contamination at glob
 al scale
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-225@cern.ch
DESCRIPTION:Speakers: Dr. NAVARRETE\, Manuel (National University of Mexic
 o\, Mexico)\nAs a result of plus than two thousand nuclear tests performed
  since 1945\, two war actions and few accidents in nuclear reactor\, it do
 es already exists a radioactive contamination at global scale. This contam
 ination has been accumulated mainly in marine sediments\, because sea is a
 bout 80% of planet surface\, and solid fission products released by nuclea
 r explosions are transported by wind first and then by rain to liquid and 
 solid portions on earth\, while gaseous fission products are diffused in t
 he atmosphere. In this way\, heavy\, high yielding fission products\, such
  as Cs-137 get marine sediments\, where they are found mixed with heavy ra
 dioactive natural elements such as U\, Th and their also radioactive decay
  products. But since alkaline are so abundant on earth\, it is also found 
 natural radioactive isotope K-40\, 0.0118% of isotopes forming K element\,
  with half life 1.28x10E9\, in the time range of planet age and elements o
 rigin. So\, one easy way to assess both the importanceand evaluation of ra
 dioactive contamination at global scale\, should be to establish a radioac
 tive contamination factor (RCF) as a percentage of Cs-137 contaminant radi
 oactivity in marine sediments\, compared to K-40 natural radioactivity pre
 sent from the very beguinning of earth\, both expressed as Bq per gram of 
 sediment. In the frame of these rather general considerations a research p
 roject has started in Mexico whose varied purposes are: to characterize se
 a regions in both vast litorals in the country\, by its natural K-40 radio
 activity present in sea salts\, as well as to determine if Cs-137 traces p
 roduced by recent radioactive contamination have reached their coasts. Als
 o\, to assess the Cs-137 traces already present in marine sediments as a r
 esult of more than two thousand nuclear test explosions performed till now
 \, rather than contamination produced by four main accidents in nuclear re
 actors during the last 60 years. It is proposed a radioactive contaminatio
 n factor obtained from samples taken up in both coasts during the last two
  years\, which it should be very useful in two ways: first to assess the r
 eal danger of radioactive contamination already present by comparing with 
 natural radioactivity\, and second to assess the growth\, equilibrium or d
 rop of radioactive contamination \, given that nuclear energy is still the
  best option to solve the large energy demand foreseen in the near future.
 \n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=225&sessionId=2
 6&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=225&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Gas-phase chemistry of carbonyl complexes formed in hot-atom react
 ions with short-lived isotopes of a Cf-252 fission source
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-24@cern.ch
DESCRIPTION:Speakers: WANG\, Yang (Institute of Modern Physics\, Chinese A
 cademy of Sciences\, China)\, Prof. QIN\, Zhi (Institute of Modern Physics
 \, Chinese Academy of Sciences\, China\, China)\nA new chemical system of 
 metal carbonyl complexes was used for studying the gas-phase chemical beha
 vior of Mo\, Tc\, and Ru isotopes with a low temperature on-line isotherma
 l gas chromatography apparatus. Carbonyl complexes were synthesized using 
 hot atom gas chemical reactions with carbon monoxide and a 252Cf fission s
 ource. On-line isothermal chromatography (IC) experiments\, on Teflon and 
 quartz surfaces showed that short-lived Mo isotopes can form carbonyl comp
 lexes which are very volatile and interact most likely in physisorption pr
 ocesses. Deduced adsorption enthalpies of Mo carbonyls varied between -37
 ±1kJ/mol and -39±1kJ/mol. Furthermore\, the adsorption enthalpies of Tc 
 and Ru carbonyls were determined to be -37±2 kJ/mol and -36±2 kJ/mol\, r
 espectively. The speciation of studied carbonyls is still missing. The des
 cribed data give great hope that this compound class might be well suited 
 for future study of nuclear and chemical properties of the transactinide e
 lements seaborgium\, (Sg\, Z=106)\, bohrium (Bh\, Z=107)\, hassium (Hs\, Z
 =108)\, and possibly also meitnerium (Mt\, Z=109).\n\nhttp://indico.cern.c
 h/contributionDisplay.py?contribId=24&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=24&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Coprecipitation of Radionuclide Microquantities on Chitosans of Di
 fferent Molecular Masses in Solutions
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-26@cern.ch
DESCRIPTION:Speakers: Prof. KULYUKHIN\, Sergey (Frumkin' Institute of Phys
 ical Chemistry and Electrochemistry\, Russian Academy of Sciences\, Russia
 )\nThe current approaches to spent nuclear fuel treatment lead to the occu
 rrence of radionuclides in repositories and ponds for the storage of fuel 
 elements. In addition\, radionuclides\, including the above-mentioned ones
 \, are components of low-activity liquid waste. Despite the efforts taken 
 to localize radioactive compounds\, they penetrate into the environment\, 
 including the World Ocean. The usage of chitosans and their derivatives as
  flocculants in sewage water purification from heavy metals\, dyes\, and s
 urfactants is reported in [1\, 2]. The advantages of ashless organic copre
 cipitators over inorganic ones are described in [3]. The authors showed th
 at the degree of Pu extraction from 0.01 M solutions of HNO3 on high-molec
 ular chitosan (HMC) with MM = 15105 g/mol and low-molecular chitosan (L
 MC) with molecular masses (MM) = 5103 g/mol is 95% to 99%. Simultaneous
 ly\, it was established that the coprecipitation degree of 60Co и 54Mn ra
 dionuclides ranged from 78% to 85%\, and that of 90Sr and 137Cs was 25-30%
 \, irrespective of the MM of the chitosans and the solution compositions. 
 The data on the behavior of other radionuclides during flocculation on chi
 tosans is unavailable in the literature. \n\nBased on the above considerat
 ions\, the aim of this study was to study the behavior of radionuclides du
 ring coprecipitation on chitosans from solutions of complex chemical compo
 sitions. The possibility of 233U\, 239Pu\, 241Am\, 152Eu\, 90Sr\, 90Y\, an
 d 60Co coprecipitation on chitosans of different MM was studied. \n\nAt fi
 rst\, the solubility of the obtained chitosans in different media was stud
 ied. It was shown that HMC and LMC were insoluble in distilled water and d
 issolved well at рН \n\nhttp://indico.cern.ch/contributionDisplay.py?con
 tribId=26&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=26&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:The Thermal Decomposition of CH3131I in a Gas Phase
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-27@cern.ch
DESCRIPTION:Speakers: Prof. KULYKHIN\, Sergey (Frumkin' Institute of Physi
 cal Chemistry and Electrochemistry\, Russian Academy of Sciences\, Russia)
 \nThe localization of volatile radioactive iodine compounds by various sor
 bents from vapor-gas media is a vital issue for environmental protection d
 uring both irradiated nuclear fuel reprocessing and accidents at nuclear p
 ower enterprises\, including nuclear power plants (NPPs).\n\nThe thermal d
 ecomposition of methyl iodide CH3131I\, a volatile radioactive iodine orga
 nic compound\, in a gas flow in the presence of various modifications of "
 Fizkhmin"TM granulated materials based on silica gel impregnated with d-el
 ements were studied. \n\nTest facility included the following basic parts:
  rotameters\; a CH3131I generator\; scrubber with water\; the heating furn
 ace of mine type\;  composite materials under study\; the thermocouple\; a
  column with SiO2-Cuo\; scrubber with 0.05 M Na2SO3 solution\; the heating
  furnace of tubular type\; columns with SiO2-AgNO3. \n\nIt was found that 
 in the absence of "Fizkhmin"TM material\, the degree of the decomposition 
 of CH3131I  (10 mg) in air (flow rate 4.5–5.5 cm/s and time of the air f
 low presence in the heating zone 1.0 – 1.5 s) was equal to (7-10)% at
  (540  10)оС\, ~(70-75)% at (640  10)оС\, and ~(97-99)% at (770 
  15)оС. \n\nIn the presence of silica gel granules measuring 1.0-3.0 
 mm\, the degree of the decomposition of CH3131I (10 mg)  in air (linear fl
 ow rate 4.8–5.2 cm/s and time of the air flow presence in the heating zo
 ne 1.0–1.1 s) was equal to (2-3)% at (240  10)оС\, ~(10-15)% at 
 (340  10)оС\, ~(75-80)% at (440  10)оС\, and ~(97-99)% at ~(540 
  10)оС. Silica gel granules allow decreasing the CH3131I thermal deco
 mposition temperature in an air flow by ~200оС.\n\nIn the presence of "F
 izkhmin"TM granulated materials impregnated with Ni compounds or Ni-Cu mix
 ture (8-10 wt.% and granule size 1.0–3.0 mm)\,  the degree of the decomp
 osition of CH3131I (10 mg)  in air (linear flow rate 4.8–5.2 cm/s and ti
 me of the air flow presence in the heating zone 0.8–1.1 s) was equal to 
 \n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=27&sessionId=26
 &confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=27&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Testing the feasibility of 44mSc/44Sc as a potential in vivo gener
 ator for PET imaging and an alternative to the existing 44Ti/44Sc ?
DTSTART;VALUE=DATE-TIME:20120917T101500Z
DTEND;VALUE=DATE-TIME:20120917T103000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-20@cern.ch
DESCRIPTION:Speakers: Dr. HUCLIER-MARKAI\, Sandrine (Laboratoire Subatech\
 , UMR 6457\, Ecole des Mines de Nantes /CNRS/IN2P3 / Université de Nantes
 \, 4 Rue A. Kastler\, BP 20722\, F-44307 Nantes Cedex 3\, France.)\nThe us
 e of radionuclides as potential therapeutic radiopharmaceuticals is increa
 singly investigated. Scandium isotopes (44Sc\, 47Sc) become more easily av
 ailable and their properties are convenient for either PET imaging or radi
 otherapy. Notably\, the half-life of 3.97 h of 44Sc and its high positron 
 branching (94%) lead us to consider this isotope for application in TEP ra
 diopharmaceuticals. The high energy and high intensity ARRONAX cyclotron p
 roduces 44Sc together with its isomeric state 44mSc (T1/2=2.44 d) that may
  stimulate its use as a potential in vivo generator. For in vivo generator
 s\, it is not only the log K of complexation between the metal ion and the
  chelator that is important\, but also whether the daughter radionuclide s
 tays inside the chelator after decay of the parent radionuclide. From our 
 previous work [1]\, we showed that the DOTA chelator exhibit the higher co
 mplexation constant value with Sc compared to other often used ligands suc
 h as DTPA\, NOTA\, … In the perspective of medical applications\, the Sc
 (III)-DOTA complex is stable over several days in the presence of a bone m
 imic and in rat serum. DOTA is also a good chelator of Ho and Nd but again
 st all expectations\, it was evidenced that 166Ho\, from 166Dy/166Ho in vi
 vo generator was released from DOTA [2]. It was evidenced that was not due
  to the low recoil energy (Q=0.486 MeV) but due to a “post-effect” as 
 shown previously for the 140Nd/140Pr generator with an even lower recoil e
 nergy (Q=0.222 MeV) [3]. The post-effect is attributed to the physico-chem
 ical process occurring after the primary radioactive decay (EC\, IT\, Auge
 r electron …). \nThis work presents the production route (targetry\, ext
 raction and purification) of 44mSc/44Sc at the ARRONAX facility and examin
 es the effect of the recoil energy and the “post-effect” on 44mSc-DOTA
  complex in the aim of establishing an in vivo 44mSc/44Sc generator.\n44mS
 c/44Sc production\, Extraction and Purification \nFor this study\, we have
  produced limited amount of scandium. A typical irradiation corresponds to
  30 min at 0.1 µA during  33 MBq of 44Sc are produced. The 44Sc/44mSc act
 ivity ratio is found to be 50 at EOB. The extraction/purification process 
 developed lead to a radionucledic purity of 100% and 43Sc\, 46Sc\, 48Sc\n\
 nhttp://indico.cern.ch/contributionDisplay.py?contribId=20&sessionId=15&co
 nfId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=20&sessionId=15
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Experimental Investigation on Cryogenic Adsorption of Low-concentr
 ation Hydrogen from Helium by MS5A
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-21@cern.ch
DESCRIPTION:Speakers: Ms. QIAN\, xiaojing (China Academy of Engineering Ph
 ysics\, China)\nTritium extraction system (TES) is one of the most importa
 nt components in the helium cooled solid breeder(HCSB) test blanket module
 s (TBMs) of ITER. TES will extract various isotopic species of hydrogen by
  the liquid nitrogen cooled molecular sieve adsorber beds (CMSB). The glob
 ular molecular sieve 5A(MS5A) with the diameter of 3~5 mm was selected as 
 the candidate for the CMSB in TBM TES. The MS5A was studied by means of th
 e thermogravimetic analysis(TGA) and thermal desorption spectroscopy(TDS).
  The adsorption property of the adsorbent was also investigated in continu
 ous He-H2 purge gases with a flow rate of 33.6 L/min. The durableness of M
 S5A was assessed according to the runtime of ITER. The results show that M
 S5A can extract traces of hydrogen from helium effectively\, furthermore\,
  the content of hydrogen was quite high in the regenerated gases of CMSB a
 fter saturated adsorption. The adsorbent can stand the test during the run
 ning of ITER. Therefore the MS5A could recover low concentration hydrogen 
 effectively and reliably from the purge gases of the TBM during the operat
 ion of ITER.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=21&
 sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=21&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Recoil and conversion electron implications to b
 e taken into account in the design of therapeutic radiopharmaceuticals uti
 lising in vivo generators
DTSTART;VALUE=DATE-TIME:20120917T130000Z
DTEND;VALUE=DATE-TIME:20120917T132000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-22@cern.ch
DESCRIPTION:Speakers: Prof. ZEEVAART\, Jan Rijn (Necsa\, South Africa)\nTh
 e use of radionuclides as potential therapeutic radiopharmaceuticals is in
 creasingly investigated. An important aspect is the delivery of the radion
 uclide to the target whereby the radionuclide is not lost from the chelati
 ng agent. For in vivo generators it is important whether the daughter radi
 onuclide stays inside the chelator after decay of the parent radionuclide.
  In our previous work\, we showed that the classical recoil effect for β 
 decay only applies to decays with a Q value higher than 0.6 MeV. The loss 
 of the daughter nuclide by a DOTA (1\,4\,7\,10-tetraazacyclododecane-1\,4\
 ,7\,10-tetraacetic acid) chelator was measured for the 166Dy/166Ho generat
 or (Q = 0.486 MeV) and the 90Sr/90Y generator (Q = 0.546 MeV) - transition
  via the Auger process is absent. It was found that 72% of the daughter (1
 66Ho) was liberated from the DOTA chelator\, in contrast to our recoil cal
 culations but corresponding to the ratio of transition of holmium atoms vi
 a the Auger process. For the β 90Sr/90Y generator a 1% release from the D
 OTA chelator was recorded as compared to the estimated 10.2% from the β c
 ontinuum spectrum of 90Sr. The discrepancy between the experimental and th
 eoretically calculated release can be explained by a correction of the che
 mical bond energy to 4.4 eV.\n\nReference\; JR Zeevaart\, Z Szucs\, S Taka
 cs\, J van Rooyen\, DR Jansen. Recoil and conversion electron implications
  to be taken into account in the design of therapeutic radiopharmaceutical
 s utilising in vivo generators. Journal of Labelled Compounds and Radiopha
 rmaceuticals\, 2012\, 55\, 115-119\n\nhttp://indico.cern.ch/contributionDi
 splay.py?contribId=22&sessionId=17&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=22&sessionId=17
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INAA for discriminationg geographic origin of Brazilian rice
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-223@cern.ch
DESCRIPTION:Speakers: Dr. ELIAS\, Camila (University of São Paulo\, Brasi
 l)\, Prof. DE NADAI FERNANDES\, Elisabete (University of Sao Paulo\, Brasi
 l)\nThe concentration of chemical elements in plants and in their edible p
 arts varies according to the plant genotype\, soil fertility\, environment
 al factors and agricultural practices. Based on such relation\, chemical e
 lements have been used to discriminate the origin of food\, identifying sp
 ecies or variety\, cultivation system and geographic region\, amongst othe
 r characteristics. Trace elements are especially interesting for discrimin
 ating the geographic origin\, since their availability for plants is norma
 lly connected to the geology and genesis of soils. As a staple food worldw
 ide\, rice has already been studied by different analytical techniques for
  tracing origin. Here\, instrumental neutron activation analysis was appli
 ed for evaluating Brazilian rice samples\, in order to identify chemical e
 lements with potential for discriminating geographic origin. Sampling was 
 performed directly in the consumer market of Piracicaba city\, São Paulo 
 State\, tracking the origin back to the processing unit. Emphasis was give
 n to commercial brands from Rio Grande do Sul\, the state with the main pr
 oduction of rice in Brazil. At total\, twelve municipalities of Rio Grande
  do Sul were represented by the sampling procedure\, comprising the region
 s west\, south and east of the State. After processing in a rotor mill\, s
 amples were irradiated at a thermal neutron flux of 8x1012 cm-2 s-1 for 8 
 hours and radioactivity was counted in HPGe detectors at decay times of 4\
 , 7\, 15 and 30 days. Concentrations of chemical elements were assessed by
  the k0 method\, allowing the determination of As\, Br\, Co\, Cs\, K\, Mo\
 , Na\, Rb and Zn. The clearest separation was observed for Na\, which pres
 ented systematically higher concentrations in rice samples originated from
  the east part of Rio Grande do Sul\, i.e. close to the Atlantic Ocean. Ho
 wever other chemical elements also demonstrated to be useful for discrimin
 ating the geographic origin.\n\nhttp://indico.cern.ch/contributionDisplay.
 py?contribId=223&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=223&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:A Solid-State NMR Study of the Complexation of 109Cd with Isosacch
 arinic Acid
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-28@cern.ch
DESCRIPTION:Speakers: Dr. EVANS\, Nick (Loughborough University\, UK)\nThe
  binding of 109Cd to isosaccharinic acid using advanced solid state NMR te
 chniques was examined. The complexes\, as well as ISA itself\, were analys
 ed at 3 different pHs (7\, 10 and 13). Various solid-state NMR techniques 
 were used. CP-MAS provided C-13 spectra of the complexes and the related d
 ipolar dephasing method helped to determine the assignment of CH and CH2 g
 roups. Slow sample spinning provided sufficient spinning side bands to all
 ow the extraction of the CSA values. Experimental compared with calculated
  techniques were also carried out using Gaussian\, Herzfeld Berger and Sim
 pson programmes to look at differences in the spectra but also the CSA of 
 the nuclei in the complex. The spectra of ISA at the various pHs were obta
 ined first. Spectra were then obtained for the metal-ligand complexes. The
 se spectra have enabled more detailed theories to be drawn up on the natur
 e of the binding of radionuclides to polyhydroxylated carboxylic acids at 
 varying pH.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=28&s
 essionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=28&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Radionuclide Production at Accelerator with High
  Power Targets
DTSTART;VALUE=DATE-TIME:20120919T094000Z
DTEND;VALUE=DATE-TIME:20120919T100000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-29@cern.ch
DESCRIPTION:Speakers: Dr. ZHUIKOV\, Boris (Institute for Nuclear Research 
 of Russian Academy of Sciences\, Russia)\nThe isotope production facility 
 at 160 MeV proton beam of linear accelerator in the Institute for Nuclear 
 Research of Russian Academy of Sciences (Troitsk) has the following charac
 teristics providing high power irradiation:\n-	4-cooling of the targets
  (from 1 to 14 targets at one time)\;\n-	slanting 26o-angle beam on the ta
 rget\;\n-	lithium beam window between accelerator vacuum and cooling water
  of the target cell\;\n-	a system of 4 cooled graphite collimators with th
 ermocouples monitoring the beam shape directly before the targets\;\n-	bea
 m sweeping providing heat distribution.\nGeneral requirements for target m
 aterials at high intensity accelerator beams are the following: high cross
 -section  of the radionuclide in the particle energy range\; high abundanc
 e of the main producing material\; known and acceptable non-radioactive im
 purities\; high temperature stability\; high heat conductivity\; high radi
 ation stability\; low vapor pressure\; low interaction with target shell o
 r cooling water\; low toxicity of the main material and impurities in case
  of medical isotope production\; acceptability for radiochemical processin
 g.  A compromise between these requirements is to be provided in the most 
 cases. Calculation with ANSYS program ensures the correct choice of target
  material and irradiation regime.\nHigh yields are resulted in producing 8
 2Sr from metallic Rb-target in stainless steel shell\, 117mSn from Sb-cont
 aining targets in graphite\, Nb- or Mo-shells\, 225Ac and 223Ra from Th-ta
 rget in graphite\, Nb- or Mo-shells\, 22Na from Al-target\, 103Pd from Ag-
 target\, 72Se from GaAs-target\, 68Ge from GaNi\, etc.`\nNew approaches ar
 e considered to irradiate cycling liquid rubidium targets to produce large
  amounts of 82Sr\, and cycling lead-bismuth targets for radionuclide produ
 ction and on-line extraction.\n\nhttp://indico.cern.ch/contributionDisplay
 .py?contribId=29&sessionId=24&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=29&sessionId=24
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Pd-based intermetallic targets for high intensity irradiations
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-94@cern.ch
DESCRIPTION:Speakers: Mr. USOLTSEV\, Ilya (Paul Scherrer Institut\, Switze
 rland)\nI. Usoltsev1\,2\, R. Eichler1\,2\, J.P. Omtvedt4\, O. V. Petrushki
 n3\, D. Piguet1\, A. V. Sabel’nikov3\, A. Türler1\,2\, G. K. Vostokin3 
 \, A. V. Yeremin3\n\n1Paul Scherrer Institut\, CH-5232 Villigen PSI\, Swit
 zerland \n2University of Bern\, CH-3012 Bern\, Switzerland\n3Flerov Labora
 tory of Nuclear Reactions\, Joint Institute for Nuclear Research\, 141980 
 Dubna\, Russian Federation\n4University of Oslo\, 0316 Oslo\, Norway\n\nTh
 e stability of actinide targets during the irradiation with intense heavy 
 ion beams is a prerequisite to successful experiments with super heavy ele
 ments [1]. Due to higher thermal conductivity\, electrical conductivity an
 d mechanical stability metallic targets are suggested to be superior to th
 e widely used nowadays solely electroplated ones. Recently we proposed a s
 imple method which allows producing Pd-based intermetallic targets for hig
 h intensity irradiations [2]. Based on the molecular plating technique [3]
  followed by coupled reduction [4] this method was successfully applied to
  different lanthanide and actinide isotopes. 3 m Pd backing foils were 
 found to be the most suitable for preparing pinhole-free targets [5].\nFir
 st irradiation experiments with intermetallic targets were carried out in 
 November 2011 at the Oslo Cyclotron Laboratory\, University of Oslo\, Norw
 ay. 0.73 mg/cm2 238U/Pd target was irradiated at the MC-35 Scanditronix cy
 clotron using a 0.5 A proton beam with cyclotron energy of 30 MeV. \nTw
 o 243Am/Pd intermetallic targets (0.85 and 1.7 mg/cm2) have been prepared 
 and irradiated at the U-400 cyclotron at the Flerov Laboratory of Nuclear 
 Reactions in March 2012 for several days with intense beams of 48Ca. Both 
 243Am targets were characterized by alpha-particle spectroscopy and light 
 microscopy before and after irradiation. For direct comparison\, the perfo
 rmance of a ‘classical’ electroplated 243AmO2/Ti target was examined.\
 n\nThis research project was supported by Swiss National Science Foundatio
 n grant 200020_126639.\n\n[1] R. Eichler\, et al.\, Nature\, 447 (2007) 72
 .\n[2] I. Usoltsev\, Attempts to produce intermetallic targets for heavy i
 on irradiations\, 4th International Conference on the Chemistry and Physic
 s of the Transactinide Elements\, 5-11 September 2011\, Sochi\, Russia. \n
 [3] W. Parker\, et al.\, Nucl. Instr. and Meth. 26 (1964) 61.\n[4] S. Möb
 ius\, L. Hellwig\, C. Keller\, J. Less-Common Met.\, 121 (1986) 43.\n[5] I
 . Usoltsev\, et al.\, Preparation of Pd-based intermetallic targets for hi
 gh intensity irradiations\, Nucl. Instr. and Meth. A (2012)\, 10.1016/j.ni
 ma.2012.06.060.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=
 94&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=94&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:LECTIO MAGISTRALIS - Chemistry in Italy during the late 18<sup>th<
 /sup> and 19<sup>th</sup> Centuries
DTSTART;VALUE=DATE-TIME:20120916T160000Z
DTEND;VALUE=DATE-TIME:20120916T164500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-0@cern.ch
DESCRIPTION:Speakers: Prof. BELLOBONO\, Ignazio Renato ()\nIn the first pa
 rt of the presentation\,  the birth of ELECTROCHEMISTRY (1799-1800\; March
  20th\, 1800) and the entirely innovative work of Alessandro Volta\, based
  on the conversion of chemical into electrochemical energy\, by what will 
 be called pila di Volta (electrochemical cell)\, followed by the reverse p
 rocess studied by Luigi Valentino Brugnatelli (electrolysis and electrolyt
 ical cell) will be outlined. The epistemological significance of this disc
 overy\, which even preceded the atomic theory\, and which will be followed
 \, just one century later (December 14th\, 1800)\, by the revolutionary Ma
 x Planck’s  idea of the energy quantum\, will be discussed\, leading us 
 to the second part of the talk.\n	About 40 years before the birth of RADIO
 CHEMISTRY\, a great debate was taking course in CHEMISTRY\,  concerning th
 e essence itself of this new-born science\, from the question of atomic an
 d molecular weights to periodical properties of the elements and their com
 pounds. Even if about further four decades before\, the Avogrado’s princ
 iple\, based on Gay-Lussac’s work\, had been established\, a great confu
 sion existed. The first to have envisaged the potentiality of Avogadro’s
  principle and its correctness has been a young researcher\, Stanislao Can
 nizzaro\, born in Palermo  (July 13th 1826)\, who won the chair of chemist
 ry in 1855\, at the University of Genoa. In this University\, he published
  in 1858 Sunto di un Corso di Filosofia Chimica\, in which he gave the out
 most value to Avogadro’s principle\, by considering that if two gases\, 
 in the same temperature and pressure state\, contain the same number of mo
 lecules\, the ratio of their two volumes gives directly the ratio of their
  molecular weights (what we now call formula weights).\n During the presen
 tation of these principles by Cannizzaro\, four years after Avogado’s de
 ath\,  at the first International Congress of Chemistry of Karlsrule\, in 
 1860\, where also Dmitrij Ivanovič Mendeléev and Julius Lothar Meyer wer
 e present\, the latter addressed to Cannizzaro a well known appreciation (
 we were blind\, and you gave us back our sight). Interpretation of CHEMIST
 RY on the light of Periodic Table of elements was the necessary presupposi
 tion\, 36  years later\, to the birth of RADIOCHEMISTRY.\n	In the third pa
 rt of the talk\, some leading Italian chemists\, organic chemists particul
 arly\, who contributed to the growth of Chemistry throughout the 19th cent
 ury\, will be presented.\n	At the end\, the epistemological connection wit
 h the outstanding development of Science in the early decades of the 20th 
 century will be briefly commented.\n\nhttp://indico.cern.ch/contributionDi
 splay.py?contribId=0&sessionId=4&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=0&sessionId=4&c
 onfId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Investigation of uranium contamination in ground water of southwes
 t Punjab using EDXRF technique
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-221@cern.ch
DESCRIPTION:Speakers: Dr. ALRAKABI\, Muhanad (Department of Physics\, Al M
 ustansiriya University\, Baghdad\, Iraq. Department of Physics\, Panjab Un
 iversity\,Chandigarh\,India)\nThe Energy-dispersive X-ray fluorescence tec
 hnique (EDXRF) is used for elemental analysis of the samples collected fro
 m the ground water and the canal water in the Bathinda district of Punjab 
 state\, India. The residues obtained after drying the water samples are an
 alyzed using the EDXRF spectrometer consisting of 42Mo-anode X-ray tube eq
 uipped with selective absorbers as an excitation source and an Si(Li) dete
 ctor. The maximum concentrations of 35Br\, 38Sr and 92U elements are obser
 ved to be 5543\, 6165 and 212 g/L\, respectively\, in shallow ground wa
 ter samples and 20\, 200 and 5 g/L\, respectively\, in the canal water 
 samples. The observed concentrations of these elements show positive corre
 lation with the Total Dissolved Salt (TDS) content of the ground water. To
  investigate the flyash from the coal-fired thermal power plants as a poss
 ible source of ground water contamination\, the water samples collected fr
 om the surroundings of the power plants and the flyash samples are also an
 alyzed. The elemental analysis rule out the possibility of flyash as a pos
 sible source of ground water contamination. The canals reaching the Malwa 
 region are based on Sutlej river and the canal water is used extensively f
 or irrigation. Samples collected from different locations of industrial wa
 ste water drains sinking into Sutlej river near Phagwara and Ludhiana were
  also analyzed. It is concluded that the industrial drains lead to uranium
  contamination in Bathinda. The presence of uranium in the ground water in
  the southwest Punjab due to weathering of granite rocks with high radioac
 tivity content (uranium concentration ~8 ppm) at Tosham hills (distance ~ 
 200 km from Bathinda) is rather unlikely in the absence of very supportive
  conditions\, viz.\, large water body with abnormal pH values and ground w
 ater flow from Tosham hill region to southwest Punjab. As the uranium cont
 amination is occurring over vast regions of ground water\, the source is l
 ikely to be not localized one. Southwest Punjab consists of Sutlej-Ghaggar
  plain. The soils in the region have largely developed on alluvium deposit
 s up to depth of thousands of feet and evidences like high concentration o
 f soil radioactivity or radon also do not favour existence of natural uran
 ium ore deposits in Bathinda. It is a rich agricultural area cultivated wi
 th the help of extensive irrigation made possible by the canal water from 
 the Sutlej river. The soils in the region are calcareous and contain urani
 um ~ 3-5 ppm. The ground water level is in the region is in general shallo
 w. The irrigation schemes are mainly based on extensive network of canal w
 ater. The irrigation water percolating through the soil dissolves carbon d
 ioxide produced from the plant root respiration and the microbial oxidatio
 n of the agricultural matter and results in carbonic acid. The carbonic ac
 id reacts with the calcium carbonate (calcareous soil) to produce bicarbon
 ate\, which leaches uranium from soils and sediments to the ground water. 
 Further\, the use of agricultural additives like phosphates fertilizers (u
 ranium concentration ~ few tens of ppm) enhances the uranium and chemical 
 concentrations in the ground water. Due to minimal use of ground water\, t
 he chemical contamination in ground water is increasing.\n\nhttp://indico.
 cern.ch/contributionDisplay.py?contribId=221&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=221&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Labeling of radiopharmaceuticals with Iodine-124
  and their clinical applications
DTSTART;VALUE=DATE-TIME:20120917T124000Z
DTEND;VALUE=DATE-TIME:20120917T130000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-163@cern.ch
DESCRIPTION:Speakers: Dr. PILLARSETTY\, Naga Vara Kishore (Memorial Sloan-
 Kettering Cancer Center\, USA)\nIodine isotopes (I-123\, I-125 & I-131) ha
 ve greatly contributed toward expanding the applications of isotopes in me
 dicine\; these applications range from ex vivo radioimmuno assays to in vi
 vo SPECT imaging. Iodine-124 (t1/2 = 4.2 d\; b+ 23%) was long considered a
 n impurity in iodine-123 production\, has lately seen a renaissance in its
  applications as a PET isotope in clinics due to the ability to produce us
 able quantities on small hospital-based cyclotrons. This presentation will
  present an overview of current approaches for production and isolation of
  iodine-124 and methods for incorporation of iodine-124 onto small molecul
 es\, peptides and antibodies. Direct labeling and indirect labeling method
 s for radioiodination of biological molecules will be discussed in detail.
  The later part of the talk will exemplify the impact of Iodine-124 based 
 PET radiopharmaceuticals in the clinical setting. Specific examples of pre
 -clinical and clinical applications including [124I]-NaI for measuring MAP
 K inhibition and sensitization to radioiodine therapy\, [124I]-PU-H71 - a 
 small molecule inhibitor of Hsp90 for measuring drug pharmacokinetics and 
  predicting response to therapy and [124I]-G250-a radioiodinated antibody 
 against CAIX antigen for detecting renal cell carcinoma will be presented.
 \n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=163&sessionId=1
 7&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=163&sessionId=1
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Study of Uranium Behavior in Lignite Sediments from Ruprechtov Nat
 ural Analogue Site
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-68@cern.ch
DESCRIPTION:Speakers: Mr. PIDCHENKO\, Ivan (Saint-Petersburg State Univers
 ity\, Russia)\, Dr. SUKSI\, Juhani (University of Helsinki\, Finland)\nStu
 dy of uranium oxidation states in natural objects is important to estimate
  radioecological impact of U and as a natural redox monitor for assessing 
 geological sites considered for long-term highly radioactive waste storage
 . In this work we studied U oxidation state distribution in the sediment s
 amples by wet chemistry and synchrotron radiation method XAS. Novel wet ch
 emical method for separating U(IV) and U(VI) from solid samples was develo
 ped and utilized. Two lignite samples having 172 and 539 ppm of U collecte
 d from the sediment layer of the Ruprechtov natural analogue site in Czech
  Republic were studied by described methods. Redox processes during U extr
 action has been monitored using 236-U(IV) and 236-U(VI) tracers. Ascorbic 
 acid was used as selective reducing agent for Fe(III) to minimize its oxid
 izing effect on U(IV). XAS showed for both samples\, that bulk of U in the
  samples is U(IV). Dissolution experiments showed that U(IV) amount varied
  widely resulting from the strong oxidation caused by Fe3+. Use of ascorbi
 c acid reduced considerably the effect of Fe3+ on U redox balance: about 7
 5% of U after samples’ extraction was found in U4+. 234-U/238-U activity
  ratios (AR) in U(IV) and U(VI) fractions were used as an additional monit
 or for U redox processes taking place during materials extraction. AR in U
 (IV) fraction\, which is less than 0.5\, did not change due to extraction 
 induced oxidation\, whereas in U(VI) fraction AR was observed to decrease 
 dramatically\, depending on the amount of U(IV) oxidised during the extrac
 tion. AR for U(VI) was found below unity after 10 min extraction with pure
  acid solution but with addition of ascorbic acid AR increased up to 2. Re
 sults showed good agreement with lignite samples from other regions of Rup
 rechtov site.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=68
 &sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=68&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Radiochemical neutron activation analysis: the c
 ontinuous need of this analysis mode
DTSTART;VALUE=DATE-TIME:20120919T131000Z
DTEND;VALUE=DATE-TIME:20120919T133000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-227@cern.ch
DESCRIPTION:Speakers: Prof. KUCERA\, Jan (Nuclear Physics Institute\, AS C
 R\, CZ-25068 Husinec-Rez 130\, Czech Republic)\nAttempts are being made to
  replace radiochemical neutron activation analysis (RNAA) by other analyti
 cal techniques capable of low-level element determination\, such as variou
 s modes of atomic absorption spectrometry (AAS) for single-element determi
 nation\, various modes of mass spectrometry\, especially inductively coupl
 ed plasma mass spectrometry (ICP-MS) for multielemental analysis and/or by
  accelerator mass spectrometry (AMS) for long-lived radionuclides. The rea
 son is that that the use RNAA is associated with a higher work-load and ra
 diation burden for personnel compared  with non-destructive\, instrumental
  neutron activation analysis (INAA)\, and sometimes also with the use of c
 hemicals that are considered to be not environmental friendly (e.g.\, orga
 nic solvents). However\, RNAA remains to be a method of choice\, especiall
 y for low-level\, low-uncertainty determination of selected elements\, and
  in selected applications. The continuous need of RNAA has been accentuate
 d by a recent recognition of neutron activation analysis (NAA) as primary 
 method of measurement [1]\, disregarding whether INAA or RNAA is employed.
  It has been demonstrated that RNAA is the most powerful means of optimiza
 tion of NAA in terms of achieving the lowest element detection limits and 
 uncertainty of measurement [2\,3].  Examples are presented of superior low
 -level determination of\, e.g.\, silicon\, vanadium\, manganese\, nickel\,
  selenium\, iodine\, rhenium\, mercury in biological materials and determi
 nation of REE in geochemical and cosmochemical samples by RNAA. The major 
 application fields involve biomedicine\, agriculture\, and chemometry\, na
 mely certification of reference materials. Recent trends and achievements 
 in RNAA are also briefly mentioned\, e.g.\, a fast decomposition of biolog
 ical materials by alkaline-oxidative fusion\, new and/or amended separatio
 n methods\, such as replacement of liquid-liquid extraction by solid phase
  extraction\, use of nanoparticles\, and use of “green” chemistry in s
 eparation of elements and their radionuclides.\nReferences\n1. Robert R. G
 reenberg\, Peter Bode\, Elisabete A. De Nadai Fernandes\, Neutron activati
 on analysis: A primary method of measurement. Spectrochim. Acta Part B\, 6
 6 (2011) 193–241.\n2. Jan Kučera\, Rolf Zeisler\, Do we need radiochemi
 ci separation in neutron activation analysis? J. Radioanal. Nucl. Chem.\, 
 262 (2004) 255–260. \n3. Jan Kučera\, Methodological developments and a
 pplications of neutron activation analysis. J. Radioanal. Nucl. Chem.\, 27
 3 (2007) 273–280.\n\nhttp://indico.cern.ch/contributionDisplay.py?contri
 bId=227&sessionId=25&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=227&sessionId=2
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - Recent advances in nuclear data research for med
 ical radionuclide production
DTSTART;VALUE=DATE-TIME:20120919T060000Z
DTEND;VALUE=DATE-TIME:20120919T063000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-120@cern.ch
DESCRIPTION:Speakers: Prof. QAIM\, Syed M. (Forschungszentrum Jülich\, Ge
 rmany)\nNuclear data play a key role in the optimisation of production rou
 tes of medical radionuclides. In general\, the production data of all comm
 only used diagnostic and therapeutic radionuclides are well known. The int
 ernational activities to standardise those data will be reviewed. Furtherm
 ore\, some recent efforts to develop alternative routes of production of a
  few widely used radionuclides\, such as 99mTc and 68Ga\, will be briefly 
 discussed.\nRegarding research oriented radionuclides\, great demand exist
 s for novel positron emitters\, e.g. to study slow biological processes an
 d to quantify dose distribution in internal radiotherapy. Some recent stud
 ies related to the development of 64Cu (T½ = 12.7 h)\, 124I (T½ = 4.2 d)
 \, 86Y (T½ = 14.7 h)\, etc. will be described as typical examples. In gen
 eral\, the low-energy (p\,n) reaction on  highly enriched corresponding ta
 rget isotope is successfully utilized. However\, for production of several
  positron emitters\, intermediate energy reactions are preferable. Another
  area of increasing interest is internal radiotherapy and the choice lies 
 on low-range highly ionising radiation emitters\, i.e. low-energy β-\, α
  and Auger electron emitters. In recent years a large number of charged-pa
 rticle induced reaction cross section measurements have been performed\, e
 specially to produce some important therapeutic radiolanthanides with high
 er specific activity than in reactor production\, though only with partial
  success. Cross section measurements to develop some novel therapeutic rad
 ionuclides have been challenging\, and interdisciplinary techniques were e
 mployed. This will be exemplified by studies on a few radionuclides\, such
  as 67Cu (T½ = 2.6 d\; Eβ- = 577 keV)\, 225Ac (T½ = 10.0 d\; Eα = 5830
  keV) and 193mPt (T½ = 4.3 d\; Auger electrons).\nThe future perspectives
  of medical radionuclide production will be considered. The potential of u
 se of high energy protons and heavier mass projectiles will be discussed.\
 n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=120&sessionId=23
 &confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=120&sessionId=2
 3&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Research Alliance for Validation of PGAA Actinide Nuclear Data
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-121@cern.ch
DESCRIPTION:Speakers: Mr. GENREITH\, Christoph (Institute for Energy and C
 limate Research\, IEK-6: Nuclear Waste Management and Reactor Safety\, For
 schungszentrum Jülich GmbH\, 52425 Jülich\, Germany)\nA Memorandum of Un
 derstanding for close collaboration in the field of prompt gamma neutron a
 ctivation analysis (PGAA) has been formulated and signed by several instit
 utions. This research alliance includes at the moment FZJ and FRM II from 
 Germany\, BNC from Hungary\, and LBNL\, and will be extended to LLNL and N
 IST from USA as well as JAERI from Japan. Besides development of PGAA and 
 their application in various fields the generation and validation of nucle
 ar data for actinides is in focus to update neutron capture cross sections
 \, energies\, and intensities for prompt and delayed gamma ray data. These
  data are important input e.g. for simulation of GENIV reactor neutronics\
 , nuclear waste management\, safeguards applications and clearance and dec
 ommissioning of nuclear installations.\n5 to 10 mg actinide-oxide powder w
 as encapsulated in aluminum or quartz and exposed to a directed cold neutr
 on beam at the research reactor in Budapest and at FRM II\, Garching. Opti
 mization of the sample preparation as well as irradiation conditions led t
 o an improvement in overall uncertainty and accuracy. Experimental data we
 re corrected for neutron self-absorption and gamma attenuation in the samp
 le and container. Revised nuclear data will be incorporated in existing nu
 clear data tables and compilations.\nProgress of experimental work will be
  reported and discussed.\n\nhttp://indico.cern.ch/contributionDisplay.py?c
 ontribId=121&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=121&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Isotopic composition of uranium in aerosol sam
 ples collected at 120 km south-southwestern of Fukushima before and after 
 the nuclear power plant accident
DTSTART;VALUE=DATE-TIME:20120921T104000Z
DTEND;VALUE=DATE-TIME:20120921T105500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-122@cern.ch
DESCRIPTION:Speakers: Dr. SHINONAGA\, Taeko (Helmholtz Zentrum München\, 
 German Research Center for Environmental Health\, Institute of Radiation P
 rotection\, Germany)\nThe isotopic composition of uranium (U) in aerosol s
 amples collected before and after the accident of the Fukushima Daiichi nu
 clear power plant (FDI-NPP)\, occurred on March 11\, 2011\, was studied. T
 he aerosol samples were collected on filters by an air sampling system in 
 Tokai\, Japan (at 120 km south-southwestern of the FDI-NPP). The filter sa
 mples were divided into several parts and U isotopic composition in each f
 ilter was analyzed. After ashing the filter samples at a high temperature\
 , the filters were dissolved into acid solutions. Uranium was then chemica
 lly separated from the matrix using ion exchange and chromatographic resin
 s. After repeated purification of U\, the isotopic ratios were measured by
  sector field inductively coupled plasma mass spectrometry (SF-ICPMS). The
  compositions of U in the samples collected after the accident show that n
 on-natural U existed in the aerosol. The results of series measurements of
  radioactive materials before and after the accident indicate that the rad
 ioactive materials released from the FDI-NPP into the atmosphere were tran
 sported to the sampling station in Tokai\, a place at 120 km distance from
  the FDI-NPP\, within a day.\n\nhttp://indico.cern.ch/contributionDisplay.
 py?contribId=122&sessionId=31&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=122&sessionId=3
 1&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:NukWik – A Tool for Collaboration and Sharing Teaching Material 
 in Radiochemistry
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-123@cern.ch
DESCRIPTION:Speakers: Mr. NORÉN\, Henrik (University of Oslo\, Norway)\, 
 Mr. LERUM\, Hans V. (University of Oslo\, Norway)\nMany institutions acros
 s Europe (and elsewhere) teach radiochemistry\, more or less with the same
  content. At most institutions\, the teaching material has been created an
 d developed in-house through many years and frequently through many genera
 tions of teachers. In most cases\, the material is not publicly available.
  However\, from time to time institutions have to create new courses or at
  least update existing ones\, which can be a large and time-consuming unde
 rtaking. For radiochemistry teaching\, which in many places is only taught
  to small groups of students\, justifying the personnel and other costs of
  developing teaching material and methods can be prohibitively difficult\,
  and will frequently be done by idealistic individuals on their own time. 
 \n\nAs part of the CINCH project [1] for developing teaching and training 
 in Radiochemistry in Europe\, we have therefore developed an open platform
  for sharing teaching material and even active collaboration across instit
 ute/university borders. The platform is run on a wiki engine and is called
  NukWik [2]. The best known example of a wiki is Wikipedia [3]. \n\nIn bri
 ef\, a wiki can be described as an editable web site. To edit a wiki there
  is no need to know complicated computer code or similar (e.g. HTML)\, in 
 most cases it is done in a simple and easy to understand web-page interfac
 e. Content can be added or edited by any member of the wiki user-group pro
 vided an internet connection is available. Content is coordinated by links
  between the pages in addition to different categories. Categorising the w
 iki-pages is very important\, as this is one of the most common ways to se
 ek out relevant information. Furthermore\, each wiki-page has an associate
 d discussions page. This can be used by teachers to discuss how to improve
  and use the material\, e.g. a specific laboratory exercise. \n\nWith NukW
 ik\, teachers can share and collaborate on anything from a given calculati
 on exercise to complete courses\, including extensive laboratory exercises
 . Institutions will of course still "own" their own courses and students\,
  but teaching material and experience can be shared. In this way one can m
 ake better courses with updated and relevant content without single-handed
 ly taking the full burden of time and resource costs. \n\nOf course\, NukW
 ik only works if those using it are willing to freely share their material
  and experience. If you are such a person\, please do not hesitate to log 
 on and/or contact us!\n\nReferences:\n[1]	CINCH is a 7th Framework Program
  of the European Commission (Euratom)\, project web-page is located at htt
 p://cinch-project.eu/index.php \n[2] 	https://wiki.uio.no/mn/safe/nukwik/i
 ndex.php/NukWik\n[3]	http://en.wikipedia.org/wiki/Main_Page\n\nhttp://indi
 co.cern.ch/contributionDisplay.py?contribId=123&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=123&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Thermochromatography study of volatile Telluri
 um species in various gas atmospheres.
DTSTART;VALUE=DATE-TIME:20120919T110000Z
DTEND;VALUE=DATE-TIME:20120919T111500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-124@cern.ch
DESCRIPTION:Speakers: Dr. MAUGERI\, Emilio Andrea (PSI\, Switzerland)\nLea
 d-Bismuth Eutectic has been proposed as spallation neutron target and as a
  coolant for Accelerator-Driven System. One of the main issues of using LB
 E is related to the production of Polonium and its potential release. \nTe
 llurium was chosen as surrogate in order to designing experimental set-ups
  for investigating gas-phase chemical properties of Polonium and its compo
 unds.\nCarrier-free amounts of elemental Tellurium\, Tellurium oxides and 
 hydroxides formed at 950 °C in various flowing carrier gasses were studie
 d by thermochromatography in quartz glass columns.\nPartitioning of the va
 rious compounds in quartz glass column was deduced measuring the -emiss
 ion from the long-lived 123mTe at 212 KeV.\nEnthalpies of adsorption of Te
 \, TeO\, TeO2 and TeO3 on quartz surface were deduced from the observed de
 position temperatures using a Monte Carlo method. The potential chemical r
 eactions occurring at different temperature are discussed.\n\nhttp://indic
 o.cern.ch/contributionDisplay.py?contribId=124&sessionId=24&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=124&sessionId=2
 4&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Determination of Boron distribution in Co-Re alloys
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-125@cern.ch
DESCRIPTION:Speakers: Dr. SZENTMIKLÓSI\, László (Centre for Energy Rese
 arch\, Hungarian Academy of Sciences\, Hungary)\nCo-Re based alloys are be
 ing developed at the TU Braunschweig to supplement Ni-based Superalloys at
  ultra-high temperature (>1200°C) applications. Grain boundaries in these
  polycrystalline alloys are strengthened by boron. Boron is known to segre
 gate to grain boundaries in Ni-alloys and improve low temperature ductilit
 y. The mechanisms to strengthen the grain boundaries are being explored fo
 r the Co-Re alloys. To have a better understanding of the effect\, a set o
 f experimental alloy was manufactured with known added boron amounts rangi
 ng from 50 to 1000 ppm. However\, as boron is volatile\, the quantity rema
 ined in the alloy is presumably lower than added.\n\nThe aims of the prese
 nt experiments were to quantify the boron content by PGAA\, and to map its
  distribution in the alloys\, looking for signs of segregation. Thanks to 
 the high cross-section of the 10B(n\,alpha gamma)7Li reaction\, we could d
 etect boron already in a few ppm quantity\, based on its 477.6 keV gamma-r
 ay. A complementary technique\, solid state nuclear track detectors (SSNTD
 ) was used to map the near-surface boron density. The alpha particles\, em
 itted from the same nuclear reaction\, create tracks in the SSNTD\, if we 
 make a close contact between a polished surface of the sample and the trac
 k detector during the irradiation. The track detectors were etched in hot 
 NaOH and imaged with an optical microscope. An attempt was also made to ha
 ve a closer look to the boron-spots with SEM\, giving far better spatial r
 esolution than a conventional microscope.\n\nSeveral measurements have alr
 eady been carried out at the PGAA beamline of the Budapest Neutron Center.
  In some samples the segregation was clearly detectable. This information 
 allows the material scientists to develop a new generation of materials.\n
 \nhttp://indico.cern.ch/contributionDisplay.py?contribId=125&sessionId=26&
 confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=125&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Skills and Knowledge Structure Needs - End-users
 ' View
DTSTART;VALUE=DATE-TIME:20120920T130000Z
DTEND;VALUE=DATE-TIME:20120920T132000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-265@cern.ch
DESCRIPTION:Speakers: Prof. HANSON\, Bruce (University of Leeds)\nThe CINC
 H project aims to coordinate education in nuclear chemistry\, both at PhD 
 and undergraduate levels\, within the EU and Russia\; targeting doctoral\,
  masters’ students and research workers. Including these students into t
 he system should increase attractiveness of the studies of nuclear chemist
 ry and thus enlarge the source of highly qualified professionals for the f
 uture employers.\nAcross the EU and Russia there is a varied level of trai
 ning available. In the UK\, there exists a well established base for nucle
 ar education available from a wide number of universities\, at both underg
 raduate and post graduate level\; funded by the RCUK and privately through
  student fees. On the whole this follows a 4+4 (MSc/MEng + “long” PhD)
  version of Bologna. Although some institutions still offer the classic 2 
 year MSc in nuclear related topics. Due to the large number of courses on 
 offer\, the provision of nuclear training is market driven\, with students
  choosing on the basis of attractiveness to industry. Industry is supporti
 ve of this approach as it means that they do not have to bear the cost of 
 education.\nAcross the EU we need to move to similar position\, so that in
 dustry will able to recruit from a large pool of qualified graduates. The 
 issue facing most EU countries is that there are not enough higher educati
 onal institutions capable of delivering nuclear education\, and in the cas
 e of CINCH nuclear and radiochemistry education\, to offer the necessary d
 iversity and numbers of students to satisfy demand. The solution is to for
 m a consortium that offers the full range of subjects required and with ea
 ch member offering courses that match their speciality. This is the model 
 being developed by CINCH for nuclear and radiochemistry.\n\nhttp://indico.
 cern.ch/contributionDisplay.py?contribId=265&sessionId=29&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=265&sessionId=2
 9&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - <sup>68</sup>Ge-<sup>68</sup>Ga production revis
 ited: new excitation functions\, target preparation and separation chemist
 ry
DTSTART;VALUE=DATE-TIME:20120919T063000Z
DTEND;VALUE=DATE-TIME:20120919T065000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-127@cern.ch
DESCRIPTION:Speakers: Prof. HERMANNE\, Alex (Cyclotron lab\, Vrije Univers
 iteit Brussel\, Belgium)\nA. Hermanne1\, R. Adam-Rebeles1\, P. Van den Win
 kel1\, L. De Vis1\, R. Waegeneer1\, F. Tarkanyi2\, S. Takacs2\, M.P. Takac
 s3.\n\n1 Cyclotron Laboratory\, Vrije Universiteit Brussel (VUB)\, Belgium
 .\n2 Institute of Nuclear Research of the Hungarian Academy of Sciences (A
 tomki)\, Debrecen\, Hungary.\n3 Institute of Physics\, University of Debre
 cen\, Hungary\n\nThe use of 68Ga (T1/2= 67.7 m\, &beta+ decay branching 89
 .1%) for clinical diagnostic PET imaging is increasing.\nThe fact that it 
 can be obtained from a generator system with long lived 68Ge (T1/2 = 288 d
 ) as parent and its versatile chemistry could make it the PET analogue of 
 the 99Mo-99mTc pair.\nThe preferred route to produce 68Ge is intermediate 
 energy proton bombardment of Ga-containing targets. The long half-life how
 ever means that long irradiations at high particle flux are needed to prod
 uce enough activity for a useful generator (typically 750 MBq). We develop
 ed high beam power withstanding targets using electro-deposition of Ga/Ni 
 alloy (70/30%) on industrially used thick Cu backings covered by a 20 μm 
 protective Au layer. Using AC Constant Current Electrolysis (current densi
 ty 34 mA/cm2) a uniform layer containing 51 mg/cm2 Ga is deposited in 7 h 
 from an acid bath containing Ga2SO4\, NiSO4 and H2SO4.\nUsing thin Ga/Ni t
 argets produced with this technique (6 mg/cm2 Ga) we measured cross sectio
 ns for reactions\, induced by protons (up to 65 MeV) and deuterons (up to 
 50 MeV)\, producing &gamma-emitting radioisotopes with halflife longer tha
 n 2 h. With a stacked foil irradiation\, followed by high resolution &gamm
 a-spectrometry\, excitation functions for 68\,69Ge\, 66\,67\,72Ga\, 69m\,6
 5Zn were determined\, relative to the monitor reaction natCu(p or d\,x)62Z
 n. The results are compared to the scarce literature values while from der
 ived thick target yields possibilities to use the deuteron reaction are di
 scussed.\nA PC-controlled automated set up for delivery of nca 69Ge is dev
 eloped and implemented in an industrial system ready to be mounted in a ho
 t cell.\nThe target layer is dissolved in a mixture of H2SO4 and H2O2 usin
 g a heated\,flow trough stripper. Prior to the extraction into toluene\, c
 oncentrated HCl is added (normality of the solution 0.4 M HCl). The back e
 xtraction of the nca 68Ge is performed using very diluted HCl. As a last p
 urification step\, a cation exchange column is used to adsorb traces of Ga
  and Ni. Samples are collected for radionuclide and chemical purity analys
 is. The 40 ml bulk is passed trough a 0.22 μm filter for final filtration
 -sterilisation. \nOverall chemistry yield\, tested by 69Ge tracer\, is hig
 her than 90 %.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=1
 27&sessionId=23&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=127&sessionId=2
 3&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - Prompt Gamma Activation Analysis using High-Flux
  Cold Neutron Beam
DTSTART;VALUE=DATE-TIME:20120920T060000Z
DTEND;VALUE=DATE-TIME:20120920T062000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-128@cern.ch
DESCRIPTION:Speakers: Dr. REVAY\, Zsolt (Technische Universität München\
 , Germany)\nThe Forschungsneutronenquelle Heinz Maier-Leibnitz at Garching
  (FRM II) is one of the largest neutron research centers in the world with
  almost 30 high-end instruments. The Prompt Gamma Activation Analysis (PGA
 A) facility is located at the cold neutron beam with a flux of 6 x 10^10 c
 m-2 s-1\, the highest beam flux reported. The instrument has been reconstr
 ucted recently to enable elemental analyses and irradiations with this str
 ong beam\, too. High-flux PGAA made possible new applications\, but also i
 ntroduced brand new challenges\, which are discussed in the presentation. 
 \n\nThe contribution of the background in the prompt gamma spectrum reduce
 d significantly thanks to reconstruction of the shielding of the instrumen
 t. The excellent signal-to-background ratio allows the measurement of samp
 les with the masses of less than a milligram\, which is practically imposs
 ible in weaker beams. For this purpose\, it was necessary to find signific
 antly lighter materials for sample packing. The reconstruction of the samp
 le holder from less massive components is also planned to further reduce t
 he spectral background. The use of smaller target quantities also makes po
 ssible the efficient measurement of radioactive materials and the counting
  of their signals above the elevated baseline from to the original activit
 y.\n\nThe new PGAA instrument has been used for high-flux irradiations and
  elemental analyses of a series of different samples successfully. Air fil
 ters with pollution contents as low as a milligram or less were analyzed\,
  and more than 10 components were determined with fair uncertainties. The 
 most sensitive elements (B and certain rare-earths) were found to be in am
 ounts of less than 100 pg. The elemental compositions of micro-meteorites 
 with masses of 300–1000 g were determined\, and they were classified 
 based on the results. In the frame of a large international collaboration\
 , nuclear data for transuranium actinides have been remeasured. The plans 
 of further improvements and other possible utilizations of the high-flux P
 GAA facility will also be discussed.\n\nhttp://indico.cern.ch/contribution
 Display.py?contribId=128&sessionId=27&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=128&sessionId=2
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Structural Transformations in Metallic Iron under the Action of Ex
 ternal Irradiation
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-129@cern.ch
DESCRIPTION:Speakers: Prof. ALEKSEEV\, Igor (Radium Khlopin Institute\, Ru
 ssia)\nUsing several modes of Mossbauer spectroscopy\, after effects have 
 been studied of irradiating metallic iron with 1) thermal neutrons (fluenc
 e of 1.8∙E24 n∙m-2)\; 2) protons (energy\, 6.0/2.0 МeV\; fluence\, 1.
 0∙E22 p∙m-2)\; 3) deuterons (energy\, 9.0/7.3 МeV\; fluence\, 1.0∙E
 21 to 1.0∙E22 d∙m-2)\; 4) α-particles from a 238Pu source (energy\, 5
 .5. MeV\; fluence\, 2.5∙E19 α∙m-2)\; 5) 12C- and 14N-ions (energy\, 4
 7.2/0 and 58.8/0 МeV\, respectively\; fluence\, (1.6 to 8.2)∙E19 ions
 ∙m-2)\; 6) 6.1 to 8.8 МeV α-particles and 208\,212Pb\, 212\,216Po reco
 il nuclei from a 228Th-source (energy\, 0.11 to 0.17 МeV)\, the total flu
 ence being 4.5∙E18 particles∙m-2.\nThe experimental data obtained in t
 he study enabled various types of external radiation to be correlated as t
 o their radiation damage\, the effect on the structure-\, phase compositio
 n- and corrosion resistance properties of metallic iron. \nAfter irradiati
 ng with neutrons\, protons and weak deuterons (beam currents of less than 
 5 µA)\, it is only the magnetic superfine structure\, which is characteri
 stic of alpha-Fe\, that has been observed in the experimental spectra. \nI
 rradiation with intensive beams of deuterons (beam currents\, 10 to 15 µA
 )\, α-particles \, 12C- and 14N-ions leads to a structural disordering of
  the alpha-Fe lattice and to the emergence of the gamma-phase on the surfa
 ce of foils and in the near-surface area: a single component\, which is 2 
 to 3 times wider as compared to the magnetic sextet lines: is a result of 
 local heating of the lattice to high temperatures with subsequent recrysta
 llization from the “molted" volume.\nIrradiation of iron foils with reco
 il nuclei (combined with α-particles) provokes corrosion processes and is
  accompanied by an intensive oxidation of the metal.\nThe work was support
 ed by a grant from the Russian Foundation for Basic Research (12-08-00048)
 .\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=129&sessionId=
 26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=129&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Problems of determination of Tc-99 in soil and sediments
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-268@cern.ch
DESCRIPTION:Speakers: Mr. KLESZCZ\, Krzysztof (IFJ PAN – The Henryk Niew
 odniczanski Institute of Nuclear Physics\, Polish Academy of Science\, Rad
 zikowskiego 152\, 31-342 Kraków\, Poland)\, Prof. MIETELSKI\, Jerzy (IFJ 
 PAN – The Henryk Niewodniczanski Institute of Nuclear Physics\, Polish A
 cademy of Science\, Radzikowskiego 152\, 31-342 Kraków\, Poland)\nThe 99T
 c is a long lived (T1/2=2.11×105 years) fission product. It is worldwide 
 spread as  remains of global fallout. It is also released from nuclear rep
 rocessing factories and was present in nuclear accident fallout\, like Che
 rnobyl for instance. This is also a decay product decay of short lived (T1
 /2=6 h)  99mTc\, the most popular nuclear medicine isotope. The large diff
 erence in half life time reduces the activity in huge scale: 1 GBq of pare
 nt isomer state produces 3 Bq of the daughter. fallout. Since the global f
 allout was formed as a sum of deposition from hundreds individual events i
 n a course of years the resulting deposition pattern  is supposed to be ra
 ther uniform. Chernobyl fallout is much more patchy.  \nOur project was de
 voted to the recognition of the presence of 99Tc in environment of Poland.
  Samples of peat\, forest soil and litter\, sewage and river sediments wer
 e subject of our analyses.  The 99Tc is a pure beta emitter (Emax 300 k
 eV) and thus it can be measured by LSC. Due to long half life time it is a
 lso possible to measure it by means of ICP MS. In course of our analyses b
 oth techniques were applied. After mineralization and Tc separation on TEV
 A column each sample was divided into two parts: one was counted using LSC
 \, second was examined by means of ICP MS. The chemical recovery was monit
 ored using 95mTc and gamma spectrometry but an attempt was done to replace
  it by stable renium. \n	The presentation will describe the difficulties w
 hich we faced in course of the project and the ways how we solved the prob
 lems. The results of analyses will be presented as well.\n\nResearch suppo
 rted by Polish Ministry MNiSW nr N305 066936 grant.\n\nhttp://indico.cern.
 ch/contributionDisplay.py?contribId=268&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=268&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Anomalous uranium enrichment in coals from Odeř\, Sokolov Basin\,
  Czech Republic
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-167@cern.ch
DESCRIPTION:Speakers: Dr. MIZERA\, Jiří (Nuclear Physics Institute ASCR\
 , Czech Republic)\nContents of uranium in coals from Odeř in the northern
 most part of the Sokolov Basin\, Czech Republic\, reach extremely high val
 ues\, up to several wt%. The coal seam is situated in the vicinity of well
  known St. Joachimsthal uranium ore deposits. The coals from Odeř can be 
 classified as xylitic to detritic brown coal orthophase.\nThe present stud
 y has been aimed at investigation of this uraniferous mineralization by de
 tailed characterization of the anomalous coals in comparison with a repres
 entative set of Czech coals. The characterization included proximate and u
 ltimate analyses\, multielement analysis by neutron and photon activation 
 analyses\, structural characterization by infrared microspectroscopy\, and
  micropetrographic analysis.\nContents of uranium in the studied Odeř coa
 ls ranged from 45 ppm to 6 wt%\, contrary to common contents in other Czec
 h coals not reaching a ten ppm level. The anomalous uranium levels seem to
  be associated with organic matter as indicated by positive correlation be
 tween uranium and oxygen (dry\, ash free) contents in Odeř coals\, contra
 ry to other coals where the uranium content is correlated rather with the 
 mineral (clay) fraction. The infrared microspectroscopy showed that the ur
 anium enrichment was accompanied with decrease in aliphatic C-H bonds and 
 slight increase in oxygen functional groups. The observed uranium microclu
 sters are not formed by uranyl species\, but probably by uraninite. These 
 clusters with signs of strong thermal or radiolytic alteration of surround
 ing coal matter were clearly observed also by micropetrography.\nThe study
  has confirmed previously proposed explanation of uraniferous mineralizati
 on in sedimentary carboniferous substances by the mechanism of fixation an
 d reduction of soluble uranyl species (e.g.\, humic\, carbonate/hydroxo co
 mplexes) by sedimentary organic matter under diagenetic or hydrothermal co
 nditions\, and formation of uraninite. The process is accompanied with oxi
 dation of alcohol functional groups and dehydrogenation of aliphatic C-H b
 onds\, and release of molecular hydrogen and protons.\n\nhttp://indico.cer
 n.ch/contributionDisplay.py?contribId=167&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=167&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Radioanalytical determinations and radioactivi
 ty measurements in the field of Radiation Protection: the experience of th
 e Integrated Laboratory of Radioactivity Measurement and Monitoring of the
  ENEA Radiation Protection Institute
DTSTART;VALUE=DATE-TIME:20120921T081000Z
DTEND;VALUE=DATE-TIME:20120921T082500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-161@cern.ch
DESCRIPTION:Speakers: Dr. ARGINELLI\, Dolores (ENEA-Italian National Agenc
 y for New Technologies\, Energy and Sustainable Economic Development\, Rad
 iation Protection Institute\, Integrated Laboratory of Radioactivity Measu
 rement and Monitoring\, Italy)\nSince more than 40 years ENEA has been wor
 king in the field of radioactivity measurement especially for environmenta
 l and internal dosimetry monitoring purposes. This activity represents a g
 reat heritage of competences and experience\, now collected in the Integra
 ted Laboratory of Radioactivity Measurement and Monitoring of the ENEA Ins
 titute of Radiation Protection (IRP MIR)\, which acts in three different u
 nits located respectively in the ENEA Centers of Saluggia\, Casaccia and T
 risaia. Thanks to their favorable geographic positions (placed respectivel
 y in the North\, Center and South of Italy)\, these units work as a single
  one Service\, able to intervene all over the country. \nThe large set of 
 measurement systems and equipments available at IRP MIR\, together with th
 e knowhow for the application of specific techniques of physical-chemical 
 and radiochemical preparation\, allow to carry out analyses on a wide spre
 ad of different samples for the determination of a huge amount of radionuc
 lides\, particularly those of the greatest radiation protection interest. 
 IRP MIR labs are continuously subjected to internal verification through i
 ntercalibration tests and the quality of their performances are supported 
 by regular participation to qualifying exercises and proficiency tests pro
 posed by the most accredited national and international organizations\, su
 ch as PROCORAD (Association for the Promotion of Quality Control in Radiot
 oxicological Analysis) to which our Institute has been participating since
  more than 15 years\, and ALMERA (Analytical Laboratories for the Measurem
 ent of Environmental Radioactivity)\, the  international network of Labora
 tories established by the IAEA with the aim to give radioanalytical sustai
 n to the Agency\, for measurements on samples coming from contaminated are
 as\, because of accidental or intentional release of radioactivity. On beh
 alf of the Italian Government the Institute of Radiation Protection of ENE
 A is active member of ALMERA network since 2005.\nThe aim of this work is 
 to present an overview of the performances provided by IRP MIR Integrated 
 Laboratory in the field of environmental monitoring\, radiotoxicology and 
 “special matrices” radioactivity analyses\, while giving particular em
 phasis on the types of analyses where the chemical and radiochemical proce
 dures assume a role of greater significance.\n\nhttp://indico.cern.ch/cont
 ributionDisplay.py?contribId=161&sessionId=30&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=161&sessionId=3
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Fast beta-alpha-pile-up suppression electronics for super heavy el
 ement identification
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-59@cern.ch
DESCRIPTION:Speakers: Dr. DRESSLER\, Rugard (Paul Scherrer Institut\, Swit
 zerland)\nThe synthesis [1] and chemical [2] investigation of new elements
  are one of the most fascinating tasks in nuclear physics and radiochemist
 ry. Especially for the investigation of their chemical properties the unam
 ¬biguous identification of the decay of their isotopes is a very importan
 t prerequisite. The time-re¬solved spectroscopic recording of alpha parti
 cles emitted during the decay of an isotope as well as its con¬secutive d
 ecaying descendents gives the highest possible confidence to assign the ob
 served event chain to the decay of the isotope of interest. However\, the 
 formation of unwanted by-products in the used nuclear reactions leads to l
 arge amounts of unwanted events in energy regions\, where the decay of the
  inves¬tigated isotopes or their daughter nuclei is expected. Especially 
 the beta-decay of Bi-212 and the following alpha-decay of Po-212 (half-lif
 e 0.3 us) might disturb the measurement due to the consecutive emission of
  a high energetic beta- and alpha-particle. The sum of the kinetic energie
 s of both particles may exceeds 10.5 MeV if both hit the same detector wit
 hin a short time period of typically less then 1 us. Conventional spectros
 copy electronics can not resolve the consecutive hits of the beta- and alp
 ha-particle in time. This leads to so called pile-up pulse height amplific
 ation. Also the separation power of high acceptance physical mass sepa¬ra
 tors like the Berkeley Gas-filled Separator (BGS at LBNL\, USA) or the Tra
 ns Actinide Separator and Chemistry Apparatus (TASCA at GSI\, Germany) are
  not able to suppress all of these beam-like by-products. It was shown in 
 [3] that such pile-up events contribute two orders of magnitude more to th
 e event budget in the region between 8.9 MeV and 9.5 MeV than all other po
 ssible events in the course of experiments synthesized 114 at the TASCA se
 parator.\nA new and fast spectroscopic detection system PURECOLD was desig
 ned and build-up to distinguish pile-up signals from real pure alpha-event
 s at the same energy. This setup is able to record each 2 us a single even
 t with overall event rates up to 12000 per sec and per spectroscopic chann
 el. The discrimination of pile-up signals is based on the sampling of the 
 leading edge of the independently amplified fast timing signal using sixte
 en consecutive fast voltage comparators (switching time 150 ps) with a tim
 e resolution of 0.5 ns. The spectroscopic part of PURECOLD consists of two
  independently acting amplifier chains each connected to a 500000 sample p
 er second 16-bit analog digital converter to process events from 0 MeV to 
 30 MeV and from 0 MeV to 300 MeV\, respectively. Furthermore\, this system
  has the capability to measure time-wise very short consecutive alpha-deca
 ys\, which appears to be increasingly important for the dis¬covery of new
  elements and new isotopes due to the possibility to convert a second sign
 al arriving within the conversion time of the first one using the second a
 mplifier chain and analog digital converter.\n\n\nReferences:\n\n[1]	Yu.Ts
 . Oganessian\, et al.: J. Phys. G: Nucl. Part. Phys. 34 (2007) R165\n[2]	H
 . W. Gäggeler: Radiochim. Acta 99 (2011) 503\n[3]	J. M. Gates\, et al.: P
 hys. Rev. C 83\, 054618 (2011)\n\nhttp://indico.cern.ch/contributionDispla
 y.py?contribId=59&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=59&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Neutron Activation Analysis and Reference Materi
 als – Development and Perfection
DTSTART;VALUE=DATE-TIME:20120920T064000Z
DTEND;VALUE=DATE-TIME:20120920T070000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-58@cern.ch
DESCRIPTION:Speakers: Dr. ZEISLER\, Rolf (NIST\, USA)\nThis review of a 40
 -year practice in neutron activation analysis (NAA) is intended to illustr
 ate the mutual benefits drawn from the values of a unique analytical tool 
 and the enabling properties provided with the reference materials. During 
 this period NAA transitioned rapidly to instrumental multi-element procedu
 res based on high resolution gamma-ray spectrometry with germanium detecto
 rs. On the side of the reference materials substantial development of biol
 ogical and environmental SRMs by the National Institute of Standards and T
 echnology (NIST) (then the National Bureau of Standards) had begun in the 
 early 1970s. Starting with the production and certification of the first e
 ver\, natural matrix\, multi-element botanical SRM 1571 Orchard Leaves\, i
 ssued in 1971\, and followed by SRM 1577 Bovine Liver in 1972 the determin
 ation of key biological and contaminant elements\, including Ca\, Mg\, Fe\
 , Cu\, Zn\, Se\, Cr\, Cd\, As\, Pb\, and Hg could be validated. The certif
 ication had been accomplished using a broad array of analytical methods\, 
 with NAA having contributed to the majority of certified values. The need 
 for more diverse and extensively characterized SRMs to fulfill the ever-gr
 owing demands in analytical chemistry for life science research and applic
 ations has been the driving force for refinement and expansion of the NAA 
 procedures. The development of more sophisticated procedures with detectio
 n limits down to 0.1 µg/kg enabled the recent establishment of new materi
 als as benchmarks for current analytical investigations. NAA procedures pr
 ovided critical analytical data in several recent SRM developments such as
  1577c Bovine Liver\, where Ag\, As\, Cr\, and V were determined at severa
 l to tens of µg/kg levels. NAA’s performance as a primary method of mea
 surement contributed to the certification of arsenic in SRM 955c Toxic Met
 als in Caprine Blood\, SRM 2668 Toxic Elements in Frozen Human Urine\, SRM
  3262 St. John’s Wort Aerial Parts\, SRM 3532 Calcium Dietary Supplement
 \, SRM 3280 Multivitamin/Multielement Tablets\, SRM 3233 Fortified Breakfa
 st Cereal\, SRM 1845a Whole Egg Powder\, and SRM 2383a Baby Food Composite
 .\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=58&sessionId=2
 7&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=58&sessionId=27
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Selective ion exchangers for Fukushima waste effluent purification
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-55@cern.ch
DESCRIPTION:Speakers: Prof. LEHTO\, Jukka (Laboratory of Radiochemistry\, 
 University of Helsinki\, Finland)\nTwo inorganic ion exchangers manufactur
 ed by Fortum company\, Finland\, and developed in collaboration with the L
 aboratory of Radiochemistry\, University of Helsinki\, have been selected 
 for the radionuclide removal in a new purification system of Energy Soluti
 ons\, USA\, to be commissioned at the Fukushima power plant in 2012. The s
 ystem will purify approximately 200\,000 m3 of highly contaminated effluen
 ts obtained due to pumping of sea water into damaged reactors after tsunam
 i had destroyed controlled water circulation in the reactors. The two ion 
 exchangers are CsTreat® for radioactive cesium removal and SrTreat® for 
 radioactive strontium removal. The former is based on a transition metal h
 exacyanoferrate and the latter on a sodium titanate. These unique ion exch
 ange materials are produced as granules suitable for column use. \n\nCsTre
 at® and SrTreat® have been utilised in several industrial radionuclide r
 emoval processes during the last twenty years [1]. CsTreat® has been in u
 se at Loviisa NPP since 1991 for the decontamination of high-salt (ca. 200
  g/L NaNO3/KNO3) evaporator concentrates and about 1\,600\,000 litres have
  been purified with only 230 liters of CsTreat® material with a decontami
 nation factor over thousand [2]. Most recent application of CsTreat® took
  place in the decommissioning of Dounreay Fast Reactors in the UK [3].\n\n
 The selectivities of CsTreat® and SrTreat® are much higher than that of 
 common organic resins or other radionuclide-selective inorganic materials.
  For example\, the selectivity coefficient of CsTreat® over sodium (kCs/N
 a) is 1\,500\,000\, which is four orders of magnitude higher than for zeol
 ites and two orders of magnitude higher than for a silicotitanates [4]\, b
 oth of which have been used in the Fukushima waste effluent treatment. As 
 processing capacity for trace level radionuclide removal is mostly governe
 d by the selectivity\, CsTreat® can offer superior performance compared t
 o other Cs-selective materials.\n\n\nREFERENCES  \n\n1.	J. Lehto and R. Ha
 rjula: Selective Separation of Radionuclides from Nuclear Waste Solutions 
 with Inorganic Ion Exchangers\, Radiochim. Acta\, 86(1999)65.\n2.	E. Tusa\
 ,  Successful Cesium Removal Campaign at the Loviisa NPP\, Finland\, Proce
 edings of Waste Management 2011\, Tucson\, AZ\, February 27 – March 3\, 
 2011.\n3.	N.McLean\, Disposal of Bulk Sodium Coolant from the Prototype Fa
 st Reactor at the UKAEA Dounreay Site\, Scotland\, The 10th International 
 Conference on Environmental Remediation and Radioactive Waste Management (
 ICEM) \, September 4-8\, 2005\, Scottish Exhibition & Conference Centre\, 
 Glasgow\, Scotland.\n4.	E. Tusa\,  R. Harjula and  J. Lehto\, Use of novel
  highly selective ion exchange media for minimizing the waste arisings fro
 m different NPP and other liquids\, Proceedings of Waste Management 2003\,
  Tucson\, AZ\, February 23-27\, 2003\n\nhttp://indico.cern.ch/contribution
 Display.py?contribId=55&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=55&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Separation of Uranium and Polonium in drinking
  water by calix[6]arene columns
DTSTART;VALUE=DATE-TIME:20120920T091000Z
DTEND;VALUE=DATE-TIME:20120920T092500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-54@cern.ch
DESCRIPTION:Speakers: Dr. BOUVIER-CAPELY\, Céline (IRSN/PRP-HOM/SDI\, Fra
 nce)\nThe general population is chronically exposed to uranium and poloniu
 m mainly through day-to-day food and beverage intake. The measurement of t
 hese naturally-occurring radionuclides in drinking water is important to a
 ssess their health impact. The methods currently used for these analyses r
 equire tedious sample preparation techniques (evaporation\, precipitation\
 , column separation...) and long counting times by alpha spectrometry. Our
  laboratory developed calix[6]arene molecules able to entrap the actinides
  U\, Pu and Am from complex matrix like urine samples. In this work\, the 
 applicability of calix[6]arene columns for uranium and polonium analysis i
 n drinking water was investigated. The analysis of uranium in water is ver
 y simple with calixarene column\, named AQUALIX. Drinking water sample (un
 til 500 ml) can be directly loaded onto AQUALIX\, without prior specific t
 reatment except an easy step of acidification and gas extraction\, to elim
 inate soluble carbonate species. Then uranium can be eluted in acidic solu
 tion from column in order to perform the measurement by inductively couple
 d plasma mass spectrometry (ICP-MS) or alpha spectrometry. This new proced
 ure is suitable for routine analysis and requires a considerably reduced n
 umber of sample treatment steps as compared to usual procedures. In this w
 ay\, the total analysis time is around half a day by combining the separat
 ion on AQUALIX with fast ICP-MS measurement. In case of simultaneous prese
 nce of polonium and uranium in water\, the separation of both radionuclide
 s is essential due to interferences in spectrometry alpha measurement. So 
 we developed a protocol based on a first step of spontaneous deposition of
  Po on metallic disk followed by the U extraction on AQUALIX column. This 
 new procedure was applied with success to different French drinking waters
  (still mineral water\, sparkling mineral water\, tap water).\n\nhttp://in
 dico.cern.ch/contributionDisplay.py?contribId=54&sessionId=27&confId=18340
 5
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=54&sessionId=27
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Mobilisation of radionuclides and heavy metals
  from mill tailings at a former uranium mine in south east Finland
DTSTART;VALUE=DATE-TIME:20120921T075500Z
DTEND;VALUE=DATE-TIME:20120921T081000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-57@cern.ch
DESCRIPTION:Speakers: Ms. TUOVINEN\, Hanna (University of Helsinki\, Finla
 nd)\nMany new ore prospecting projects have been launched recently in Finl
 and\, seeking to exploit both metalliferous and non-metalliferous (e.g. ph
 osphate) mineral deposits. Currently there is increasing awareness of the 
 radiological impact of non-nuclear industries that extract and/or process 
 ores containing naturally occurring radioactive material (NORM). These ind
 ustrial activities may cause significant environmental problems if the was
 te generated during processing is not adequately managed. \n\nThe Paukkaja
 nvaara mining site in Eno started operation in 1959. The mine was a test s
 ite for assessing the feasibility of larger scale uranium extraction. The 
 ore was milled and enriched on site but mining proved to be uneconomic\, a
 nd so operations ceased in 1961. In the late 1970’s the entrance of the 
 mining shaft was sealed with a concrete slab and the area including tailin
 gs\, waste-water ponds etc.\, was abandoned. The site was left untouched f
 or nearly 30 years until Finnish Radiation and Nuclear Safety Authority in
 itiated a review. Their results indicated that ambient radiation levels at
  the site had increased by 0.5 µSv/h as a direct result of the earlier mi
 ning operations. Rehabilitation was completed by 1994 after which the area
  was released for outdoor use without restrictions.\n\nThe aim of this stu
 dy was to examine the potential for mobilisation of radionuclides and heav
 y metals from the mill tailings and the waste rock pile. Samples of run-of
 f sediment were collected along a transect from the waste rock to a small 
 pond (Iso Hiislampi). Depth-profiled bottom sediment samples were also tak
 en from the pond close to the mill tailings area. After pre-treatment\, ga
 mma spectrometry was used for direct determination of uranium and thorium 
 progeny (principally\, 234Th (238U)\, 235U\, 226Ra\, 210Pb and\, - 228Ac (
 228Th)). Samples were then analysed by X-ray diffraction (XRD) to determin
 e the main minerals present. Thereafter\, aqueous samples were prepared by
  microwave digestion in nitric acid allowing determination of uranium\, th
 orium and heavy metals by Inductively Coupled Plasma Mass Spectrometry (IC
 P-MS) and uranium and thorium by alpha spectrometry\, respectively. For th
 e latter method\, uranium and thorium were separated using anion exchange 
 chromatography. The use of complementary analytical techniques highlighted
  issues with complex mineralogical matrices and reduced uncertainty in the
  extent of legacy radionuclide and heavy metal contamination present at th
 e site.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=57&sessi
 onId=30&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=57&sessionId=30
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Exploitation of accelerator waste for the produc
 tion of exotic radionuclides
DTSTART;VALUE=DATE-TIME:20120919T141000Z
DTEND;VALUE=DATE-TIME:20120919T143000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-56@cern.ch
DESCRIPTION:Speakers: Dr. SCHUMANN\, Dorothea (Paul Scherrer Institute\, S
 witzerland)\nHigh-energetic protons and secondary particles produce in int
 eraction with matter – due to the broadness of the induced nuclear react
 ions – a big variety of radionuclides\, with some of them being very rar
 e\, exotic\, and\, in several cases\, difficult to be produced by compleme
 ntary reactions. Depending on the nature of the activated material\, valua
 ble isotopes\, interesting for scientific and technological applications\,
  can be extracted from samples stemming from the surroundings or component
 s of a particle accelerator\, especially if the initial proton flux is com
 parable high (in the Megawatt range). \nProminent examples are 7Be\, 60Fe\
 , 44Ti\, 26Al\, 53Mn and others\, which play an essential role for our und
 erstanding of the synthesis of elements in different stages of the stellar
  evolution. Suitable sample materials for basic studies of the key nuclear
  reactions as well precise determination of the corresponding half-lives a
 re therefore urgently needed.\nSince PSI operates the most powerful high-e
 nergetic proton accelerator world-wide\, this facility is best-suited for 
 a R&D program aimed to “mine” such isotopes. An initiative called ERAW
 AST (Exotic Radionuclides from Accelerator Waste for Science and Technolog
 y) was started in 2006 with an ESF-funded workshop in order to identify an
 d motivate potential users. After five years\, in the frame of a second wo
 rkshop\, first achievements as well as realistic future plans for front-en
 d experiments were presented.\nThe present contribution summarizes the mos
 t prominent results and gives an outlook on the upcoming experiments in th
 e frame of the ERAWAST program.\n\nhttp://indico.cern.ch/contributionDispl
 ay.py?contribId=56&sessionId=25&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=56&sessionId=25
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Biodistribution of Gadolinium-Based Contrast Agent\, and Concentra
 tion of Trace Elements in Normal and Nephrectomized Mice
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-51@cern.ch
DESCRIPTION:Speakers: Mr. WASHIYAMA\, Kohshin (College of Medical\, Pharma
 ceutical and Health Sciences\, Kanazawa University\, Japan)\nINTRODUCTION:
   Gadolinium (Gd)-based contrast agents have been used in medical MR-imagi
 ng. However\, human nephrogenic systemic fibrosis (NSF) is reported in Gd-
 based contrast agent received patients with severe renal insufficiency. A 
 depletion of endogenous Zn ion may contribute in the development of NSF. G
 adolinium has fairly high sensitivity for neutron activation analysis (NAA
 ) and it is useful to know Gd behavior in biological samples as an activab
 le tracer. In general\, NAA technique also quantitates essential trace ele
 ments in vivo such as Zn\, Mn. In this study\, we measured distribution of
  Gd and concentration of some minerals in selected tissue of four experime
 ntal conditioned mice using of NAA.\n\nEXPERIMENTS: Twenty male 8-week-old
  ICR strain mice were used in this study. Ten mice were housed as normal\,
  and another ten mice were partially nephrectomized. Five mice in each gro
 up was administered 2.5 mmol Gd/kg body weight of Gd-based contrast agent 
 intravenously. Two days after administration\, mice were sacrificed and di
 ssected. The blood\, femur\, kidney\, and liver were excised and weighted.
  The samples were freeze-dried and sealed into polyethylene bags for NAA. 
 The sealed samples\, reference materials\, and standard of Gd were irradia
 ted by neutron at Pn-2 site of Kyoto University Research Reactor Institute
 . The distribution of Gd and concentration of minerals were determined by 
 using gamma-ray spectrometry.\n\nRESULTS: The nephrectomized mice showed h
 igh Gd retention in each tissue compared to normal mice. The kidney showed
  high Gd retention behaviors due to normal process of excretion of Gd. Ske
 letal Gd distribution of nephrectomized mice were significantly higher tha
 n that of normal mice. Manganese concentrations in kidney of model mice de
 creased relative to normal mice. On the other hand\, Mn concentrations in 
 liver were comparable during four groups. Zinc concentration in the select
 ed tissue showed no difference during four groups of mice.\n\nhttp://indic
 o.cern.ch/contributionDisplay.py?contribId=51&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=51&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Sorption of Cadmium\, Nickel\, Caesium and Strontium to a Laterite
  Soil: Application of Linear Additive Model and Surface Complexation Model
 ling
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-50@cern.ch
DESCRIPTION:Speakers: Mr. ANJOLAIYA\, Olanrewaju (Loughborough University\
 , UK)\nLaterite soil obtained from Lagos\, Nigeria was comprehensively cha
 racterised to determine the organic matter content\, cation exchange capac
 ity\, surface area\, and  of mineralogical composition. The laterite was c
 onstituted mostly of Quartz (47.2 %)\, Kaolinite (42.6 %)\, Goethite (7.2 
 %)\, and hematite (2.1 %).  \nBatch sorption experiments for Cd\, Cs\, Ni 
 & Sr to the laterite were performed from pH 5 to 9\, and to a synthetic la
 terite soil prepared using commercially available analytical grade mineral
 s. The individual sorption profiles of the metals with the pure minerals w
 ere obtained\, as well as those of mixtures of the minerals in incremental
  complexity\, a Linear Additive Model (LAM) has been used to calculate the
  theoretical Rds of the mixtures from the individual Rds. Potentiometric t
 itrations of the solids were carried out to obtain log K values and proton
  exchange capacities\, and these have been applied to surface complexation
  models (SCM) using the speciation software JCHESS\, to predict sorption p
 rofiles.\nThe sorption profiles of the different metals with the natural a
 nd synthetic laterites have been compared to the profiles calculated with 
 LAM and predicted with SCM. The sorption profiles obtained from the increm
 ental complex mixtures allow for better understanding of differences betwe
 en the experimental\, calculated or predicted sorption profiles\, if any.\
 n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=50&sessionId=26&
 confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=50&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Study of the Production of Mo and Tc Medical  Radioisotopes Via Pr
 oton Induced Nuclear Reaction on natMo.
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-53@cern.ch
DESCRIPTION:Speakers: Dr. ALHARBI\, Abeer (Princess Nora University\, Saud
 i Arabia)\n99mTc radioisotope is a very important medical radioisotope for
  diagnostic tests. In this work an alternative root of producing this isot
 ope\, either directly or through the generator 99Mo (99mTc ) \, namely usi
 ng cyclotrons\, is introduced and discussed. The excitation functions for 
 the different proton-induced nuclear reactions on natMo target are measure
 d and compared with some previously measured data. This study aims to rele
 ase some contradictions between the existing data\, and to give a reliable
  data set for the production of 99mTc and some other isotopes of importanc
 e in nuclear medicine beside some impurities. Some monitoring reactions on
  Al And Cu targets are also measured and compared with the recommended IAE
 A data sets\, in order to give high degree of consistency to our results. 
 The present excitation functions confirms some previously measured sets\, 
 while contradicts with others. Therefore\, further expermintal studies are
  needed to obtain a recommended cross-section values for the production of
  99Mo\, 94gTc\, 95gTc and 99mTc via proton induced reactions. Theoretical 
 code calculations using TALYS code are performed and show a good consisten
 cy with the measured cross section values. The code calculations can be us
 ed for cross section estimations\, when no enough experimental data are ex
 isting. Furthermore\, the integral or thick target yields are estimated ba
 sed on the measured excitation functions for all the investigated reaction
 s.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=53&sessionId=
 26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=53&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Synthesis of Silica-coated Bimetallic Nanopart
 icles as Radiotracers
DTSTART;VALUE=DATE-TIME:20120919T150500Z
DTEND;VALUE=DATE-TIME:20120919T152000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-52@cern.ch
DESCRIPTION:Speakers: Dr. JUNG\, Sung-Hee (Korea Atomic Energy Research In
 stitute\, Korea)\nBimetallic nanoparticles of Au with Ag\, Cu\, and Ir wer
 e synthesized by irradiating aqueous bimetallic ions with gamma radiation 
 that generates hydrated electrons neutralizing the metal ions to a particl
 e form. The bimetallic nanoparticles were coated with SiO2 making them che
 mically and physically stable when released into the environment and most 
 of industrial processes for hydrodynamic investigation. Their shell and co
 re diameters were recorded by TEM as 100~112 nm and 20~50 nm\, respectivel
 y. The nanoparticles were then bombarded with neutrons in a research nucle
 ar reactor in order to make them radioactive. The radioactive nanoparticle
 s can play a role of radiotracers in refinery/petrochemical industries as 
 well as in environmental resource hydrodynamic investigation.\nRadioisotop
 es are useful due to their same chemical properties as those of stable iso
 topes and higher detection sensitivity than other types of tracers. Their 
 usefulness has been demonstrated in various experiments in diverse areas i
 ncluding life science\, medicine\, and engineering. SiO2-coated radioisoto
 pe Au core-shell nanoparticles (Au@SiO2 NPs) were first synthesized by sol
 -gel reactions (the Stöber method) of aqueous Au NPs induced by irradiati
 on without reduction agents. The physical integrity of the SiO2 coated nan
 o shells in high gamma radiation dose environment was confirmed in the pre
 vious study. \nThis work reports the synthesis of radioactive silica-coate
 d bimetallic NPs (Au-Ag@SiO2\, Au-Co@SiO2\, Au-Cu@SiO2\, and Au-Ir@SiO2) b
 y the Stöber method followed by neutron irradiation. The resulting partic
 les can be used in natural resource investigations as activable tracers th
 at are to be taken from the environment and activated in a nuclear facilit
 y for quantitative estimation of the tracer as a function of time and loca
 tion.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=52&session
 Id=25&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=52&sessionId=25
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Nuclear Fuel Cycle: Processes\, critical aspects
  and perspectives
DTSTART;VALUE=DATE-TIME:20120918T135000Z
DTEND;VALUE=DATE-TIME:20120918T141000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-259@cern.ch
DESCRIPTION:Speakers: Dr. TROIANI\, Francesco (ENEA/NUCLECO SpA)\, Dr. GRA
 SSO\, Giacomo (ENEA)\nThe growing awareness of the urgent need to reduce e
 missions of greenhouse gases and to increase the security of energy supply
  are changing significantly the energy scenarios of the world and low-carb
 on energy technologies in the next future will play a crucial role. To thi
 s end\, although severe accidents occurred over the years\, many countries
  are still considering nuclear energy as an important source for power gen
 eration - economically\, environmentally and socially sustainable. Current
  technologies and the latest generation of nuclear plants offer better per
 formance and reliability for all 60 years of their useful life (and beyond
 )\, increased efficiency in the use of the fuel\, and advanced safety syst
 ems\, with very high availability factors (over 90%) and less production o
 f radioactive waste.\nHowever\, some critical points for a rapid expansion
  of nuclear energy remain. The whole nuclear power generation and the rela
 ted fuel cycle is a very complex process\, which requires large initial in
 vestments and considerable costs for a long period of operation and decomm
 issioning.\nUranium resources are limited. At the current burn rate with t
 he present technology\, the conventional resources of uranium will ensure 
 supply only for some hundred of years and the possibility that a strong ex
 pansion of nuclear energy could limit the availability of uranium on the m
 arket at competitive prices is in itself a limiting factor. \nThe enrichme
 nt process is another critical point. A large expansion of nuclear energy 
 requires more efficient technologies and further enrichment facilities. To
  lose the control of these installations increases the risk of illicit tra
 fficking of nuclear materials and the proliferation of nuclear weapons\, i
 ncluding terrorist threats. The international system of safeguards on nucl
 ear technology and materials in general ensures an adequate level of secur
 ity\, but it must be strengthened for some aspects\, avoiding the spread o
 f sensitive knowledge and technology and reinforcing the international co-
 operation. \nAnother important issue is the radioactive waste produced at 
 each stage of the fuel cycle\, which together with the plant safety is of 
 greatest concern to the public. The management and disposal of radioactive
  wastes is an essential part of the fuel cycle. Progress needs to be made 
 in building and operating facilities for the temporary storage and disposa
 l of spent fuel and high-level wastes in geological formations. \nMoreover
 \, since the irradiated fuel discharged from the present reactor fleet\, e
 ntirely made of light-water reactors\, contains significant amounts of pot
 entially recyclable combustible materials - mainly plutonium (about 1%) an
 d slightly enriched uranium (about 95%)\, while only about 3.5% are fissio
 n products and 0.1% actinides – large scale reprocessing plants to extra
 ct uranium and plutonium from spent fuel are in operation and for the futu
 re it is expected an increasing of the current capacity\, mainly related t
 o the next-generation nuclear systems.\nThey will be able to burn the most
  part of uranium\, as well as plutonium and actinides\, which are the most
  responsible for the longevity of radioactive waste. At this point the pro
 blem of long-lived waste is strongly reduced\, minimizing the need for geo
 logical repositories and current reserves of uranium will last for millenn
 ia.\nTo this aim\, several technologies are under development\, but their 
 full commercial deployment will be reached not before of some decades.\nTh
 e present work presents and discusses some critical points of current fuel
  cycle technologies and processes\, providing also an overview on the pers
 pectives for an increased sustainability - efficiency\, safety and reliabi
 lity\, economics\, waste reduction\, proliferation resistance\, etc - of n
 uclear energy in the future.\n\nhttp://indico.cern.ch/contributionDisplay.
 py?contribId=259&sessionId=19&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=259&sessionId=1
 9&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Extraction of Zr and Hf using TBP and TIOA for the chemistry of el
 ement 104 Rf
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-164@cern.ch
DESCRIPTION:Speakers: Dr. KASAMATSU\, Yoshitaka (Osaka University\,  Japan
 )\nChemical properties of transactinide elements (Z ≥ 104)\, superheavy 
 elements\, are unexpected from the properties of its homologues in the per
 iodic table due to strong relativistic effect on the orbital electrons in 
 the heavy elements. Studies on the transactinide elements have\, therefore
 \, attracted many scientists. On the other hand\, it is very difficult to 
 perform chemical experiments of these elements because of their short half
 -lives and low production rates. Rapid chemical experiments on “one-atom
 -at-a-time” basis are needed. Although there are some pioneering researc
 hes conducting chemical separations\, studies obtaining chemical constants
  in equilibrium are a few especially in solution chemistry. \nIn the prese
 nt study\, the distribution ratios in solvent extraction and distribution 
 coefficients in solid-liquid extraction were determined for Zr and Hf as t
 he homologues of rutherfordium (Rf\, Z=104) in the triisooctylamine (TIOA)
 /HCl and tributylphosphate (TBP)/HCl systems by batch method. From these r
 esults\, we discussed the chloride complexation and chemical species extra
 cted\, and determined the experimental conditions for the extraction of Rf
 . Based on the comparison of these data with those obtained for Rf\, we wo
 uld clarify the properties in the chloride complex formation of Rf. \n Two
  types of rapid extraction apparatuses are under development to obtain the
  extraction data of Rf in equilibrium. For solvent extraction\, a micro-ch
 emical tip\, Teflon capillary tube\, and micro mixer device were tested as
  a mixing section of the solvent extraction apparatus using Zr and Hf radi
 otracers. As a result\, it is found that rapid chemical reactions were obs
 erved in using the micro-chemical tip. Solid-liquid extraction apparatus w
 hich can perform rapidly solid-liquid extraction by batch method was also 
 developed. By this apparatus\, time dependence of the distribution coeffic
 ients are expected to be obtained for superheavy elements. Performance of 
 this apparatus was checked by the on-line experiment using the accelerator
 .\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=164&sessionId=
 26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=164&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Preparation of 57Co sources for Mössbauer Spectroscopy
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-93@cern.ch
DESCRIPTION:Speakers: Dr. ŻÓŁTOWSKA\, Małgorzata (National Centre for 
 Nuclear Research\, Poland)\nThe method of preparation of 57Co source appli
 ed in Mössbauer Spectroscopy was developed. This method comprised electro
 deposition of carrier-free 57Co on rhodium foil followed by thermal diffus
 ion of 57Co into rhodium matrix. A series of experiments were performed in
  order to determine the optimal conditions for electrodeposition of cobalt
  on rhodium foils 6um thick. Electrochemical cell consisting of platinum a
 node and rhodium disc as the cathode was chosen. The electrolyte was an aq
 ueous solution of ammonia citrate 25g/l\, hydrazine hydrate 25/l and carri
 er-free 57Co in the form of 57Co(II) in 0\,1M HCl. The diffusion of 57Co i
 nto rhodium lattice was carried out by annealing the foil at temperature o
 f 1100˚C at high vacuum\, in quartz tube. The 57Co active cores were enca
 psulated in cylindral Ti capsules with Be windows. The Mössbauer spectra 
 were measured to verify the quality and efficiency of the testing sources.
  The experiments performed allow making an optimum choice of the electrode
 position parameters of carrier-free 57Co on rhodium foil. The highest effi
 ciency approaching 100% and the best rate of deposition were obtained usin
 g current density 50mA/cm2 and electrolyte volume – 5ml. The best result
 s of diffusion of electrodeposition cobalt-57 onto rhodium matrix was obta
 ined in an annealing process at 1100˚C in vacuum over 10-6 hPa. The main 
 spectra parameters of the prepared sources are fairly acceptable with resp
 ect to the typical obtainable values for α-Fe absorbers in Mössbauer spe
 ctroscopy. The results obtained confirm that the deposited layer diffused 
 almost completely into rhodium matrix without substantial loss of the acti
 vity deposited.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=
 93&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=93&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Nuclear and radiochemical study of production and utilization of r
 adioactive astatine isotopes in the 7Li+natPb reaction
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-199@cern.ch
DESCRIPTION:Speakers: Dr. NISHINAKA\, Ichiro (Japan Atomic Energy Agency\,
  Japan)\nAn alpha radioactive nuclide 211At with a half-life of 7.2 h is a
  prospective candidate for utilization in targeted alpha radiotherapy. In 
 a general way\, 211At is produced through bombardment of a bismuth target 
 with 28 MeV helium ions in the 209Bi(alpha\,2n)211At reaction because of t
 he high yield required for therapeutic purpose [1]. However\, the nuclear 
 reactions using lithium ion beams\, 6\,7Li+Pb and 6\,7Li+209Bi\, provide t
 he possible production routes of 211At. Excitation functions have been ext
 ensively measured for the 6\,7Li+ 209Bi reactions to study the reaction me
 chanism involving complete fusion and breakup reaction of weakly bounded n
 uclei 6\,7Li [2-4]. For 7Li+natPb\, however\, only reports on production o
 f astatine isotopes 207-210At have been available for radiotherapy [5]. Th
 erefore\, we have measured excitation functions of 208-211At in the reacti
 on of 29-57 MeV 7Li+natPb at the tandem accelerator of JAEA-Tokai. The cro
 ss sections of radioactive products were determined by alpha- and gamma-ra
 y spectrometry. The cross sections of 211At below 45 MeV are large compare
 d with those of the other astatine isotopes 208-210At. The experimental ex
 citation functions of astatine isotopes have been compared with a statisti
 cal calculation to study the reaction mechanism. Besides\, a chemical sepa
 ration of carrier-free radioactive astatine isotopes from an irradiated ta
 rget has been studied with a dry-chemistry method. Details will be shown i
 n the presentation.\n	\nReferences\n[1] S. Lindergren\, T. Bäck\, H. J. J
 ensen\, Appl. Radiat. Isot.\, 55 (2001) 157-160\; S. Lindegren et al.\, J.
  Nucl. Med.\, 49 (2008) 1537-1545.\n[2] H. Freiesleven\, H. C. Britt\, J. 
 Birkelund\, and J. R. Huizenga\, Phys. Rev. C\, 10 (1974) 245-249.\n[3] M.
  Dasgupta et al.\, Phys. Rev. C\, 66 (2002) 04602-1-4\; M. Dasgupta et al.
 \, Phys. Rev. C\, 70 (2004) 024606-1-20. \n[4] Yu. E. Penionzhkevich et al
 .\, J. Phys. G\, 36 (2009) 025104-1-12. \n[5] K. Roy\, and S. Lahiri\, App
 l. Radiat. Isot.\, 55 (2008) 571-576\; M. Maiti and S. Lahiri\, Phys. Rev.
  C84 (2011) 067601.\n\nhttp://indico.cern.ch/contributionDisplay.py?contri
 bId=199&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=199&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Radioactivity measurement for air-dust and soil collected in easte
 rn Japan area after the nuclear accident at the Fukushima Daiichi Nuclear 
 Power Station
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-198@cern.ch
DESCRIPTION:Speakers: Mr. ZHANG\, Zijian (Osaka University\, Japan)\nOn Ma
 rch 12\, 2011\, a large amount of radioactive nuclides have been released 
 into the environment by　the nuclear accident at the Fukushima Daiichi Nu
 clear Power Station .\nOur group started radioactivity measurements for I-
 131\, Cs-134\, Cs-137 and the other radio nuclides from air dust collected
  using high-volume air sampler by germanium semiconductor detector soon af
 ter the accident. Air dust samples have been collected at some spots in ea
 stern japan periodically.  In some cases\, we have used charcoal filter to
  collect I-131 in the form of gas\, and collections of air dust by cascade
  impactor were also performed to separate air dust according to molecular 
 mass. We have already measured more than 500 air dust samples\, and we wil
 l discuss the distribution and time variation of radionuclides in the envi
 ronment.\nIn addition to gamma-ray measurement targeting I-131\, Cs-134 an
 d Cs-137\, our group has been carrying out detection of pure beta emitter 
 like Sr-89 and Sr-90 in soil and filter using chemical separation techniqu
 e. Because Sr-89 is a short life radionuclide (t1/2 = 50.5 d)\, the existe
 nce of Sr-89 represents the radionuclide is originated from the accident. 
 For this purpose\, we developed strontium isolation technique using solid-
 phase extraction method and selective detection technique of radioactivity
  of Sr-89 and Sr-90 using Cerenkov counting.\n\nhttp://indico.cern.ch/cont
 ributionDisplay.py?contribId=198&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=198&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Development of production possibilities of n.c.a radiomanganese in
  a non aggressive and toxic medium
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-147@cern.ch
DESCRIPTION:Speakers: Dr. BUCHHOLZ\, Martin (Forschungszentrum Jülich\, G
 ermany)\nIn view of new arising hybrid imaging methods\, e.g. the PET/MRT 
 combination [1]\, it is of high interest to develop new multimodal imaging
  tracers. In these imaging tracers rests the potential for the evaluation 
 of old and new contrast agents in MRT\, especially concerning new nanopart
 icle contrast agents. A large part of these newly composed MRT contrast ag
 ents are manganese based [2]. Therefore the cross sections for Cr-nat(p\,x
 n)Mn-52g\,m reactions and its byproducts (V-48\,Cr-48\,49\,51) were measur
 ed up to 45 MeV\, and a method was developed to separate n.c.a. radiomagan
 ese from bulk chromium by ion chromatography.\n\nCross section measurement
 s were conducted by the stacked-foil technique. Because of the brittle nat
 ure of metallic chromium an electrodeposition method [3] was used to obtai
 n thin metallic layers on a gold backing. Multiple foil stacks were irradi
 ated with protons of 17 or 45 MeV incident energy. The measured cross sect
 ions differ only slightly (1-10%) from literature\, except for the Cr-nat(
 p\,xn)Cr-51 reaction which shows a massive divergence (≈400%) from publi
 shed data [4]. This ascertained our previous measurements [5].\n\nFor the 
 development of the separation process cast plates of chromium were irradia
 ted with protons in the energy range of 17 to 7 MeV. These targets were di
 ssolved in fuming HCl. Bulk chromium was then separated from n.c.a. Mn-52 
 by means of ion chromatography with the cationic exchange resin DOWEX 50WX
 8. A quantitative separation was achieved with 0.1 M sulfuric acid as elue
 nt for chromium and a 0.067 M ammonia citrate solution with pH 7.3-7.4 for
  n.c.a. radiomanganese. The latter eluent is not aggressive and not toxic.
  The separation took 3-4 h and 99% of Mn-52 was eluted from the column in 
 ca. 12 ml of the eluent.\n\nReferences:\n[1] H. F. Wehrl\; B. J. Pichler\;
  Eur. J. Nucl. Med. Mol. Imaging\; 36\; (2009)\; 56-68.\n[2] D. Pan\; G. M
 . Lanza\; Tetrahedron\; 67\; (2011)\; 8431-8444.\n[3] A. Fessler\; Z. B. A
 lfassi\; S. M. Qaim\; Radiochim. Acta\; 65\; (1994)\; 207-213.\n[4] J. N. 
 Barrandon\; R. H. Spear\; Nucl. Instr. Meth.\; 127\; (1975)\; 269-278.\n[5
 ] A. T. J. Klein\; F. Rösch\; S. M. Qaim\; Radiochim. Acta\; 88\; (2000)\
 ; 253-264.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=147&s
 essionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=147&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Application of medium-energy proton beam from AIC-144 cyclotron in
  biological and environmental  studies
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-195@cern.ch
DESCRIPTION:Speakers: Ms. WÓJCIK\, Anna (1 Department of Nuclear Physical
  Chemistry\, The Henryk Niewodniczański Institute of Nuclear Physics Poli
 sh Academy of Sciences\, Cracow\, Poland 2 Faculty of Physic and Applied C
 omputer Science\, AGH University of Science and Technology\, Cracow\, Pola
 nd)\nActivation analysis is a well known analytical technique used for per
 forming both qualitative and quantitative analysis of major\, minor and tr
 ace elements in a given sample\, without or with chemical separation. Appl
 ication of protons with the energy higher than 30 MeV in activation analys
 is considerably broaden the spectra of possible reaction channels (possibi
 lity of (p\, xn) reactions\, presence of the secondary neutrons which can 
 also interact with a studied sample)\, which is always associated with som
 e difficulties in the identification of activation products. This must be 
 carefully examined in order to eliminate the existing interferences. AIC-1
 44 cyclotron at the Institute of Nuclear Physics Polish Academy of Science
  can accelerate proton up to the energy of 60 MeV while the beam intensity
  does not exceed 50 nA (which is suitable for the radiotherapy of eye mela
 noma). Since 2010 we have studied several types of biological and environm
 ental samples trying to check whether a proton beam with such intensity an
 d energy can be used in activation analysis. As a result we have selected 
 the elements which are possible to be determined under the above-mentioned
  experimental conditions. The rotating target holder enabled us to ensure 
 the same irradiation conditions for samples and standard solutions.\n\nhtt
 p://indico.cern.ch/contributionDisplay.py?contribId=195&sessionId=26&confI
 d=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=195&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Selected  Elements content in Paraguayan Wheat
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-194@cern.ch
DESCRIPTION:Speakers: Prof. FACETTI - MASULLI\, J F (Universidad Nacional 
 de Asunción - Paraguay)\nThe two fold purpose of this paper is to determi
 ne the composition of selected elements in Paraguayan wheat and flour as w
 ell as to analyse the implications of the bromine/bromate content on baker
 y products.Despite of its importance\, there is  a lack of information in 
 regard to the normal values of the concentration of minor and trace elemen
 ts  in wheat from Paraguay East Region or Eastern Paraguay (1). According 
 to that\, in this work\, selected minor and trace elements in eight variet
 ies of wheat from the center and south areas of Eastern Paraguay were anal
 yzed by XRF techniques using an Isotopic Cd Source and a XR Mo tube. The a
 nalyzed elements were K\, Ca\, Ti\, Mn Fe Cu Zn  Br Rb Sr. The materials  
 were: whole samples\,  flour\, bran and ashes of soft wheat\, Triticum Aes
 tivum subspecie  Vulgare obtained by successive milling and sieving.  Soil
 s in the Center are Rhodic Paleudult from sandstones associated with Molli
 c Paleudult as well as a small portion of LithicUpdisament. In the south (
 Itapua) dominate two type of soils: Rhodic Paleudult from basalts and Typr
 ic Kandiudox also from basalts and some sandstone. The  results (mean valu
 es) of whole samples  are as follow:\nK 1426.7±118.6 \; Ca  213.0±30.0 \
 ; Ti 7.7±0.6 \; Mn  41±3.1 \; Fe 39.1±6.6 \; Cu 5.9±1.0\;  Zn 33.0±3.
 0  \;  Br 7.5±0.7  \; Rb 4.3±0.4 \; Sr 3.1±0.4. \nThe first fraction of
  flour which came from the center of the grain were obtained after the fir
 st milling and sieving \; next grinding and sieving  yield another fractio
 n\;  after the third\, the fraction was mainly bran.  The results were in 
 good agreement with those from whole samples.  In addition XRF measurement
 s made on ashes from the grains were also coherent which the above. \nEsse
 ntial microelements like Mn Fe Cu Zn values as well as of the other analyt
 es found here are also into the range of  those from several studies  made
  elsewhere (2).\nAnother element of interest is bromine specially as KBrO3
  . The use of this compound  as an additive in the bakery dough to improve
  the whiteness and other characteristics of bread is well known. When usin
 g second class flour\, this is clearly a deceit (3). Although there are so
 me simple methods to look for the adulterant in the row dough\, no simple 
 procedure is available to detect it in the final product. This is overcome
  using XRF\, which is simple and direct\, provides the “normal” bromin
 e content of national or regional flour used in the bakery is known: this 
 is the “base line”.  A significant excess in the product means adulter
 ation.\n\nIn this regard\, samples of first quality commercial flours from
  Paraguay (N=25) and from Argentina (N=5) were also analyzed for Br and it
 s content was found to be within the normal values of bromine in Paraguaya
 n wheat and flours. However when analyzing bakery products\, bread (N=20) 
 and galletas (N=6) it was found that ~35% exceed the normal Br values show
 ing bromate malpractice.\n\nFrom dietary point of view it should be emphas
 ized that KBrO3 is a complete carcinogen and classified as showing  clear 
 evidence of carcinogenety (4) \,inducing renal cell tumors as well other t
 oxic effects. Its use as food additive has been banned(3\,5). In regard to
  Br- product of  KBrO3 decomposition\, after new evidences of its toxicolo
 gical effects at low dosis\, a provisional ADI for bromide ion of 0\,4mg/k
 g bw has been calculated  and proposed(6). Therefore it is concluded that 
 the intake due to malpraticed bakery products together with the bromide io
 n of total diet\, easily exceeds the recommended DI.  Morover the XRF tech
 nique described herein is simple\, rapid and reliable.\n\nhttp://indico.ce
 rn.ch/contributionDisplay.py?contribId=194&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=194&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Automated rapid α/SF detection system for studying aqueous chemis
 try of superheavy elements at RIKEN
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-197@cern.ch
DESCRIPTION:Speakers: Dr. HABA\, Hiromitsu (RIKEN\, Japan)\nThe extremely 
 low production yields and short half-lives of superheavy element (SHE) nuc
 lei force us to perform rapid\, efficient\, and repetitive chemical experi
 ments with single atoms. We plan to start the study of the aqueous chemist
 ry of SHEs such as 261Rf\, 262Db\, and 265Sg using the RIKEN AVF Cyclotron
 . In this work\, we have developed an automated α/spontaneous fission (SF
 ) detection system that can be coupled to various aqueous chemistry appara
 tuses. This system consists of a storage column of Ta dishes for holding s
 ample solutions\, a round table for sixteen Ta dishes\, i.e.\, a sample co
 llection port\, and sixteen detector chambers for the detection of α-part
 icles and/or SF fragments. Beside the round table\, we set up the appropri
 ate aqueous chemistry apparatus. The SCARA robot (Yamaha YK500XG) picks up
  a Ta dish from the storage column through suction and positions it on the
  round table. The table is rotated to position the dish at the desired por
 t for sample collection\, and the solution\, typically ~200 μL for each d
 ish\, is rapidly dried by using hot helium gas and a halogen heat lamp. Th
 en\, the robot transfers the dish to the detector chamber\, which is equip
 ped with a Si PIN photodiode (Hamamatsu S3204-09) and a preamplifier (Hama
 matsu H4083). The detector chamber is closed promptly and evacuated\, and 
 –50 V is applied to the detector from a complex module comprising a powe
 r source and a gate generator (Vacuum Products GG-10001). The whole system
  is controlled by a programmable logic controller (Keyence KV-3000)\, and 
 each action can be triggered by relay contact signals from a separate cont
 roller of the chemistry apparatus. The time required to start the measurem
 ent after drying the sample is about 5 s. Each detector has a counting eff
 iciency of 36%. The α-energy resolution is about 50-keV FWHM at 5.486 MeV
 .\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=197&sessionId=
 26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=197&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - Iron speciation in aqueous systems: the power of
  Mössbauer spectroscopy applied in frozen solutions
DTSTART;VALUE=DATE-TIME:20120918T095000Z
DTEND;VALUE=DATE-TIME:20120918T101000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-196@cern.ch
DESCRIPTION:Speakers: Prof. HOMONNAY\, Zoltan (Eotvos Lorand University\, 
 Hungary)\nMössbauer Spectroscopy is technique basically used for the anal
 ysis of solid systems due to the neccessity of recoilless gamma emission a
 nd absorption. 57Fe offers very convenient conditions for Mössbauer measu
 rements\, and this is why iron containing systems ranging from alloys to m
 inerals have been studied and reported in thousands of scientific papers\,
  and Mössbauer Spectroscopy became a popular and powerful method. \nAqueo
 us solutions of iron salts can only be studied in frozen state\, which pos
 es some experimental challenge\, but this opens a new window to systems ot
 herwise difficult to analyse.\nStructure of solvated ions\, species partic
 ipating in complex equilibra\, and numerous other problems can be solved b
 y quick freezing of the solution studied.\nThe technique has been applied 
 first by Attila Vertes in the late 1960s\, and most common iron salts (nit
 rate\, perchlorate\,  sulfate\, chloride\, etc.) have been thoroughly inve
 stigated.\nBeyond the regular Mossbauer parameters\, in solutions\, parama
 gnetic spin relaxation can help distinguish between various species especi
 ally between monomeric species and possible bridged dimers or oligomers. E
 valuation of Mössbauer parameters can reveal oxidation states\, coordinat
 ion numbers\, possible isomers of multi-ligand complex ions\, contribution
  of the solvent molecules in the ligand sphere\, etc.\nThe method how one 
 can use frozen solution Mossbauer spetra to identify iron species in aqueo
 us solutions will be demonstrated with special focus on iron chelates and 
 their reactions with hydrogen peroxide resulting in the formation of perox
 o adducts.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=196&s
 essionId=21&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=196&sessionId=2
 1&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Atmospheric activity concentration of radiocesium at Mikamine\, Se
 ndai and radioactivity distribution on the collection filters used in the 
 measurement.
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-191@cern.ch
DESCRIPTION:Speakers: Dr. KIKUNAGA\, Hidetoshi (Tohoku University\, Japan)
 \nThe Fukushima 1 Nuclear Power Plant suffered major damage from the 2011 
 off the Pacific coast of Tohoku Earthquake and subsequent tsunami on March
  11\, 2011 and released various radionuclides. Monitoring of environmental
  radioactivity should provide important information on the behavior of the
  radionuclides.\nTo investigate the time variation of atmospheric activity
  concentration of radiocesium\, we have regularly collected aerosol partic
 le samples at Mikamine\, Sendai from March 15\, 2011 to present. The aeros
 ol particle was collected on a cellulose-glass fiber (Advantec\, HE-40T). 
 The radioactivity of radiocesium in the aerosols collected was determined 
 by gamma-ray spectrometry using HP-Ge detectors. The atmospheric activity 
 concentrations of radiocesium were calculated as the ratio between the rad
 iocesium activity in the aerosol particle sample and the total volume of s
 ampling air. As a result\, it was found that the maximum activity concentr
 ations of radiocesium were recorded in March 20-21\, 2011 and then the atm
 ospheric activity concentrations of radiocesium roughly decreased with a h
 alf-life of 10 - 30 d.\nIn addition\, radioactivity distribution on the co
 llection filters used in the measurement was measured by using imaging pla
 te technique. The relation between the monitoring results on the concentra
 tion of radiocesium in the air and the imaging plate results are discussed
  in the presentation.\n\nhttp://indico.cern.ch/contributionDisplay.py?cont
 ribId=191&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=191&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Iodine-129 and iodine-127 in aerosols from Northern Germany
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-190@cern.ch
DESCRIPTION:Speakers: Dr. DARAOUI\, Abdelouahed (Leibniz Universität Hann
 over\, Germany)\, Ms. SCHWINGER\, Mareike (Leibniz Universität Hannover\,
  Germany)\, Dr. RIEBE\, Beate (IRS / Leibniz Universitaet Hannover\, Germa
 ny)\nI-129 (T₁/₂=15.7 Ma) is produced both naturally and as result of 
 human nuclear activities. Nowadays\, the amount of anthropogenic I-129 in 
 the atmosphere and in surface waters has continued to increase due to rele
 ases from the spent nuclear fuel reprocesssing plants\, particularly in We
 stern Europe\, from the nuclear reprocessing plants La Hague (France) and 
 Sellafield (U.K.). In the atmosphere\, iodine exists in differnt species a
 s inorganic gaseous iodine (I₂\, HI\, HOI)\, organic gaseous iodine (CHI
 ₃\, CH₂I₂\, CH₃CH₂CH₂I\, etc.) and particle associated iodine\
 ; their concentrations vary with location\, season and climate. The specia
 tion of I-129 in the atmosphere can also provide useful information about 
 sources and transfer pathways. \nIn this work\, we present the concentrati
 on of I-127\, I-129 and the ratio of I-129/I-127 in aerosol samples\, coll
 ected weekly during the year 2011 in Braunschweig\, Northern Germany. Aero
 sols were extracted from the filters using an alkaline solution and separa
 ted from the matrix elements with chloroform. The samples were analysed fo
 r I-129 by accelerator mass spectrometry (AMS)\, and for I-127 by inductiv
 ely coupled plasma mass spectrometry (ICP-MS). \nThe concentrations of I-1
 27 and I-129 in aerosol filters range between 0.4-3.7 ng/m³ and 0.06-0.7 
 fg/m³\, respectively. The I-129/I-129 ratios range between 0.7 x 10E-7 an
 d 7.4 x 10E-7. In addition\, we compare the distribution of I-129 with tha
 t of Kr-85 and Be-7. We discuss the effect of speciation of I-129 and stab
 le I-127 in the environment\, and the disequilibrium between these two iso
 topes.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=190&sessi
 onId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=190&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:66Ga-labeling of DOTA-conjugated cyclic RGDfK dimer for αvβ3 int
 egrin overexpression tumors
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-193@cern.ch
DESCRIPTION:Speakers: AVILA-RODRIGUEZ\, Miguel (N)\nAngiogenesis is an ess
 ential process in solid tumours growing beyond 2 to 3 mm3\, since diffusio
 n is no longer sufficient to supply the tissue with oxygen and nutrients. 
 Integrins αvβ3 have been shown to play an important role in a series of 
 pathological processes including angiogenesis and tumour cell metastasis. 
 It has also been shown that peptides based on the Arg-Gly-Asp (RGD) sequen
 ce have a high affinity and selectivity for αvβ3 integrins. The aim of t
 his research is to prepare and evaluate 66Ga-DOTA-Glu-[cyclo(Arg-Gly-Asp-D
 -Phe-Lys)]2 (66Ga-DOTA-E-[c(RGDfK)]2)\, as potential diagnosis agent for t
 he early and specific detection of cancers overexpressing αvβ3\, and eva
 luate its potential as possible agent for therapy. Gallium-66 was produced
  on a 11 MeV cyclotron via the 66Zn(p\,n)66Ga reaction and radiochemical s
 eparation was performed by ion exchange chromatography using a AG 50W X-4 
 cation exchange column. For radiolabelling 30 µl of the peptide conjugate
 d solution (400 ug/ml\, H2O with 1% EtOH)\, 25 μl 1 M HEPES\, pH 7.0 and 
 25 μl 0.25 M NH4OAc\, an pH 5.5\, were mixed with 66Ga stock solution (50
  µl 0.1M HCl) and incubated for 20 min at 95°C. When needed\, labelled p
 eptides were purified by SPE on an Oasis HLB cartridge\, product eluted wi
 th a small volume of 25% EtOH and diluted to \n\nhttp://indico.cern.ch/con
 tributionDisplay.py?contribId=193&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=193&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Production of Four Terbium Radioisotopes for R
 adiopharmaceutical Applications
DTSTART;VALUE=DATE-TIME:20120917T135500Z
DTEND;VALUE=DATE-TIME:20120917T141000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-192@cern.ch
DESCRIPTION:Speakers: Mr. DORRER\, Holger (Paul Scherrer Institut\, Villig
 en-PSI\, Switzerland & University of Bern\, Berne\, Switzerland)\nIntroduc
 tion: Terbium provides 4 radioisotopes\, which are suitable for different 
 diagnostic or therapeutic applications in nuclear medicine. These are 149T
 b (T½ 4.1 h\, Eα 3.97 MeV\, Iα 16.7 %) for α–radionuclide therapy\, 
 152Tb (T½ 17.5 h\, Eβ+\,av 1.08 MeV\, Iβ+ 17 %) for PET\, 155Tb (T½ 5.
 3 d\, Eγ 86.6/105 keV) for SPECT and 161Tb (T½ 6.9 d\, Eβ-\,av 0.154 Me
 V) for β--radionuclide therapy. 161Tb is similar to the clinically employ
 ed radiolanthanide 177Lu\, but emits in addition a number of conversion- a
 nd Auger-electrons.\n\nAim: The production of the four radionuclides shoul
 d be established in a quality\, which is suitable for radiolabeling of bio
 molecules.\n\nMethod: Neutron-deficient 149Tb\, 152Tb\, and 155Tb were pro
 duced at ISOLDE(CERN) by spallation reactions using 1.4 GeV protons onto a
  50 g/cm2 thick tantalum target followed by online mass separation and dep
 osition onto carrier foils.\n161Tb was obtained from neutron irradiation o
 f highly enriched 160Gd targets at the high flux reactor of ILL\, Grenoble
  or spallation neutron source SINQ\, PSI.\nChemical separation of Tb radio
 isotopes was accomplished by cation exchange chromatography using the comp
 lexing agent α-hydroxyiso-butyric acid (α-HIBA).\n\nResults: 6 MBq 149Tb
 \, 18 MBq 152Tb and 9 MBq 155Tb were obtained in ≤ 1 mL 0.15 M α-hydrox
 yisobutyrate solution.\nUp to 10 GBq 161Tb were produced from irradiated 1
 60Gd targets and obtained in 300 μL 0.05 M HCl.\nRadiolabeling of a novel
  DOTA-folate conjugate was performed with > 96 % yield at Tb:DOTA-folate m
 olar ratios 1:~59000 (149Tb)\, 1:~5500 (152Tb)\, 1:~700 (155Tb) and 1:17 (
 161Tb).\nRadiolabeling of DOTATATE was performed with > 99 % yield at 161T
 b:DOTA-Tyr3-octreotate molar ratios ≥ 1:6.\n\nConclusion: Successful pro
 duction of the Tb-radioisotopes enabled synthesis of radiolabeled DOTA-fol
 ate conjugates and their evaluation in an in vivo study.\nTest radiolabeli
 ng of DOTATATE confirmed the high specific activity of the obtained 161Tb.
 \n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=192&sessionId=1
 7&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=192&sessionId=1
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:CROCK: Crystalline Rock Retention Processes A 7th Framework Progra
 mme Collaborative Project (2011-2013)
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-115@cern.ch
DESCRIPTION:Speakers: Dr. RABUNG\, Thomas (Karlsruhe Institute of Technolo
 gy - Institute for Nuclear Waste Disposal\, Germany)\nThe EURATOM FP7 Coll
 aborative Project “Crystalline Rock Retention Processes” (CP CROCK) is
  established with the overall objective to develop a methodology for decre
 asing the uncertainty in the long-term prediction of the radionuclide migr
 ation in the crystalline rock far-field. The project is launched in respon
 se to the need identified in conjunction with selection of retention data 
 for the forthcoming crystalline host-rock HLW disposal Safety Case. The pr
 ocess of selecting a set of data for this purpose showed that the spread i
 n data is broad and that this spread in data cannot presently be related t
 o material properties or processes. Consequently\, very conservative numbe
 rs need to be used in order to be defendable within the Safety Case. \n\nT
 he project makes use of the broad set of existing analytical approaches\, 
 methodologies\, and general knowledge from decades of past investigations.
  It builds on the output and main conclusions of the 6th FP IP FUNMIG proj
 ect and the Swedish site selection program. The experimental program reach
 es from the nano-resolution to the Performance Assessment (PA) relevant re
 al site scale\, delineating physical and chemical retention processes. Exi
 sting and new analytical information provided within the project is used t
 o set up step-wise methodologies for up-scaling of processes from the nano
 -scale through to the PA relevant km-scale. Modeling includes testing up-s
 caling process and parameters for the application to PA and in particular\
 , the reduction of uncertainty.\n\nThe project started on 1st January 2011
  and will last 2 years and a half (2011-2013).The project is implemented b
 y a consortium with 10 Beneficiaries consisting of large European Research
  Institutions\, Universities and SME’s and from countries with dedicated
  crystalline host-rock disposal programs and particular competence in this
  field. National Waste Management organizations participate as associated 
 groups\, contributing with co-funding to beneficiaries\, infrastructure\, 
 knowledge and information. They also contribute together with national reg
 ulators to guidance with respect to application of the project to the disp
 osal Safety Case and scientific-technical review. \n\nThe research leading
  to these results has received funding from the European Atomic Energy Com
 munity's Seventh Framework Programme (FP7/2007-2011) under grant agreement
  No. 269658 (CROCK).\n\nhttp://indico.cern.ch/contributionDisplay.py?contr
 ibId=115&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=115&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:THEREDA – a Thermodynamic Reference Database project
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-114@cern.ch
DESCRIPTION:Speakers: Dr. ALTMAIER\, Marcus (Karlsruhe Institute of Techno
 logy\, Institute for Nuclear Waste Disposal\, Germany)\nRadioactive waste 
 poses a serious danger to the environment. Consequently\, many significant
  efforts are made to ensure the safe disposal of hazardous waste. In order
  to assess the long term safety of a repository\, geochemical model calcul
 ations are used to analyze the performance of a system and predict the amo
 unt of radionuclides potentially mobilized from a repository. For reliable
  geochemical model calculations\, a consistent\, comprehensive and well ma
 intained thermodynamic reference database is needed. The main objective of
  THEREDA is to establish a comprehensive and internally consistent thermod
 ynamic database for the geochemical modelling of near-field and far-field 
 processes occurring in the different host rock formations under discussion
 . The THEREDA database is run by the following institutions:\nGRS: Gesells
 chaft für Anlagen- und Reaktorsicherheit mbH\, Germany\nKIT-INE: Karlsruh
 e Institute of Technology\, Institute for Nuclear Waste Disposal\, Germany
 \nHZDR-IRC: Helmholtz-Zentrum Dresden-Rossendorf\, Institute of Resource E
 cology\, Germany\nTU-BAF: Technische Universität Bergakademie Freiberg\, 
 Institut für Anorganische Chemie\, Germany\nAF-Consult: AF-Consult Switze
 rland AG\, Switzerland\nTHEREDA is focusing on data for actinides\, fissio
 n- and activation products\, chemotoxic elements and the elements defining
  the matrix system\, i.e. the system of oceanic salts and cement phases. S
 pecific labels are assigned to the data included in THEREDA allowing for t
 raceability and transparency. THEREDA database is organized in a way to as
 sure that compatibility problems (e.g. arising from exclusively SIT or Pit
 zer compatible data) are managed. The database is handled by a central dat
 abank\, and made available to potential users via internet. Software tools
  are supplied to translate THEREDA into input files for commonly used geoc
 hemical modeling codes (EQ3/6\, PHREEQC\, Geochemist’s Workbench\, CHEMA
 PP\, …). \nFor more information please visit the project webpage at www.
 thereda.de where more detailed information on the THEREDA project and cont
 act addresses are given.\n\nhttp://indico.cern.ch/contributionDisplay.py?c
 ontribId=114&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=114&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Redox behavior of the Tc(VII)/Tc(IV) couple in dilute to concentra
 ted NaCl and MgCl2 solutions
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-117@cern.ch
DESCRIPTION:Speakers: Mrs. YALCINTAS\, Ezgi (Karlsruhe Institute of Techno
 logy\, Institute for Nuclear Waste Disposal\, Germany)\nFor the long-term 
 performance assessment of nuclear waste repositories\, reliable prediction
 s of radionuclide mobility have utmost importance. 99Tc is a β-emitting l
 ong-lived (T½ ~ 211.000 a) fission product highly relevant for nuclear wa
 ste disposal. Tc(VII) and Tc(IV) are the most stable and  dominant redox s
 tates of technetium under environmental conditions. Heptavalent Tc exists 
 under non-reducing conditions as the highly soluble TcO4− pertechnetate 
 anion. Technetium present in the tetravalent oxidation state\, however\, f
 orms hydrous oxides (TcO2∙xH2O(s)) which drastically limit Tc solubility
  and mobility. Because of the significant impact on Tc chemistry\, the red
 ox behaviour of the Tc(VII)/Tc(IV) couple needs to be investigated in deta
 il. In order to predict Tc behaviour for nuclear waste disposal in rock sa
 lt formations\, dedicated studies under saline conditions are required.\nI
 n this study\, the redox behaviour of the Tc(VII)/Tc(IV) couple was invest
 igated in dilute to concentrated saline systems. Reduction experiments wer
 e performed under Ar atmosphere by using different homogenous and heteroge
 neous reducing systems in NaCl (0.5 M and 5.0 M) and MgCl2 (0.25 M\, 2.0 M
  and 4.5 M) solutions to provide for repository-relevant geochemical condi
 tions. Eh and pH were measured after given aging times and the results sys
 tematised according to Pourbaix diagrams in order to assess the redox beha
 viour of technetium in highly saline systems. Technetium concentrations\, 
 redox state and aqueous speciation were analysed. The results show a clear
  effect of the specific reducing systems and ionic strength conditions on 
 measured Eh values and Tc(VII)/Tc(IV) redox transformations. The experimen
 tal data are compared to thermodynamic calculations and geochemical model 
 predictions.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=117
 &sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=117&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Novel <sup>18</sup>F-Radiochemistry
DTSTART;VALUE=DATE-TIME:20120917T122000Z
DTEND;VALUE=DATE-TIME:20120917T124000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-89@cern.ch
DESCRIPTION:Speakers: Dr. ERMERT\, Johannes (Forschungszentrum Juelich Gmb
 H\, Institut fuer Neurowissenschaften und Medizin\, INM-5: Nuklearchemie\,
  Germany)\nFluorine-18 is a widely used positron-emitting radionuclide in 
 positron emission tomography (PET) because of its ideal decay characterist
 ics. It decays by positron emission (97%) with a relatively low energy of 
 maximum 0.635 MeV ensuring highest possible resolution. The half-life of 1
 09.7 min permits extended syntheses of 18F-labelled radiopharmaceuticals a
 nd study protocols. Fluorine-18 is generated either as nucleophilic [18F]f
 luoride or as electrophilic [18F]fluorine gas ([18F]F2). The latter is gen
 erally obtained in carrier added form. This limits the attainable specific
  activity of 18F-labelled products generated by the electrophilic method. 
 High specific activity\, however\, is often critical with PET imaging. Thu
 s\, the synthesis of no-carrier-added (n.c.a.) 18F-labelled products is pr
 actically limited to nucleophilic methods. \nTherefore\, novel 18F-radioch
 emistry focuses on more efficient routes for the introduction of [18F]fluo
 ride into organic molecules. New methods are being developed for its intro
 duction into electron rich aromatic rings\, e.g. by using different types 
 of iodonium salts or triarylsulfonium salts. Recently\, the synthesis of a
  sophisticated palladium-based\, electrophilic 18F-fluorinating reagent wa
 s described started from n.c.a. [18F]fluoride which allows the synthesis o
 f electron rich [18F]fluoroaryl compounds. Concerning the 18F-labelling of
  molecules in aliphatic position new developments were made based on enzym
 atic 18F-fluorination\, the use of ionic liquids and protic solvents actin
 g as catalysts. The application of “click chemistry” and thiol-reactiv
 e labelling agents facilitate peptide and protein labelling with n.c.a. [1
 8F]fluoride. \nAll the above mentioned methods make use of the conventiona
 l formation of a C-18F bond. The easier formation of phosphorous-\, boron-
  or silicon-18F bonds led to a variety of new strategies for 18F-labelling
  of macromolecules. \nIn summary\, current and advancing radiochemical met
 hods and technologies will be presented which make use of n.c.a. [18F]fluo
 ride in the preparation of 18F-labelled radiotracers for application with 
 PET.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=89&sessionI
 d=17&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=89&sessionId=17
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Aqueous-phase chemistry of the heaviest elements
DTSTART;VALUE=DATE-TIME:20120918T075000Z
DTEND;VALUE=DATE-TIME:20120918T081000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-111@cern.ch
DESCRIPTION:Speakers: Dr. NAGAME\, Yuichiro (Japan Atomic Energy Agency\, 
 Japan)\nChemical characterization of the heaviest elements in aqueous-phas
 e experiments is performed by a partition method with single atoms\, e.g.\
 , liquid-liquid extraction\, ion-exchange chromatography\, and reversed-ph
 ase extraction chromatography. In these processes\, the behavior of the he
 aviest elements is compared with that of its lighter homologues under stri
 ctly identical conditions. Several investigations have been carried out wi
 th automated rapid chemical separation apparatuses to characterize chemica
 l properties of the heaviest elements. Typically interesting results recen
 tly obtained are that fluoride complex formation of element 104\, Rf\, is 
 significantly different from that of the homologues\, and that anionic flu
 oride complexation of element 105\, Db\, is considerably different from th
 at of the group-5 homologue Ta while the behavior of Db is similar to that
  of the lighter homologue Nb.\nDevelopment of a new apparatus based on flo
 w electrolytic column chromatography combined with ion-exchange separation
  has been recently carried out. Oxidation of element 102\, No\, has been s
 uccessfully conducted based on an atom-at-a-time scale. This approach will
  lead to new frontiers of aqueous-phase chemistry of the heaviest elements
 \; information on valence electronic structure of the heaviest elements th
 rough redox potentials will be obtained. Prospects for the future studies 
 on redox properties of the heaviest elements will be briefly considered.\n
 \nhttp://indico.cern.ch/contributionDisplay.py?contribId=111&sessionId=20&
 confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=111&sessionId=2
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Recoil-radiolabelling of nanoparticles with 7Be generated by 7Li(p
 \,n)7Be reaction in mixed powder targets.
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-110@cern.ch
DESCRIPTION:Speakers: Dr. KOZEMPEL\, Jan (Charles University in Prague\, C
 zech Republic)\nNano-sized materials have highly interesting physico-chemi
 cal properties that may be employed to great advantage in many areas. Howe
 ver\, their application in various fields of society (e.g. in consumer pro
 ducts\, including cosmetics or food) also implies safety issues. Many stud
 ies on nanoparticle toxicity have been performed\, but a basic problem reg
 arding risk assessment is nanoparticle quantification. This may easily be 
 addressed by using radiotracers and radiolabelled nanomaterials. Some indu
 strially produced nanomaterials (e.g. SiO2\, Al2O3\, or carbon-based nanop
 articles) are\ndifficult to radiolabel without significant chemical surfac
 e modification.\n\nWe present here a solution to this difficulty based on 
 recoil light-ion implantation (e.g. Be-7). An overview of different radiol
 abelling methods as well as the Be-7 ion implantation method is presented.
  Radiolabelling yields and the influence of irradiation on nanomaterials i
 s also discussed.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribI
 d=110&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=110&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Coupling actinide speciation and thermodynamic
 s: Neptunium(VI) solubility and speciation in alkaline NaCl solutions
DTSTART;VALUE=DATE-TIME:20120921T074000Z
DTEND;VALUE=DATE-TIME:20120921T075500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-113@cern.ch
DESCRIPTION:Speakers: Dr. ALTMAIER\, Marcus (Karlsruhe Institute of Techno
 logy\, Institute for Nuclear Waste Disposal\, Germany)\nIn order to assess
  the long-term safety of a nuclear waste repository it is essential to der
 ive robust predictions of radionuclide solubility and speciation. Based up
 on correct and reliable chemical models it is possible to derive comprehen
 sive sets of thermodynamic data and quantitatively analyse radionuclide be
 haviour for different scenarios. Coupling modern actinide speciation tools
  and conventional thermodynamic approaches offers important advantages for
  developing comprehensive quantitative geochemical models. The use of adva
 nced spectroscopic tools in actinide chemistry\, one main driving force fo
 r aqueous actinide chemistry over the last decade\, yields detailed molecu
 lar level information on chemical speciation and aqueous and solid phase c
 haracteristics. Conventional solubility studies allow deriving robust solu
 bility limits and information on macroscopic thermodynamic properties like
  solubility products\, complex formation constants or ion-interaction para
 meters. Improved spectroscopic information on actinide speciation will con
 sequently result in improved chemical models and thus contribute to improv
 ed thermodynamic descriptions and geochemical model predictions. \nIn rece
 nt studies of Np(VI) solubility in alkaline NaCl solutions we have success
 fully combined advanced spectroscopic studies with information from solubi
 lity studies and chemical thermodynamics. Using XAFS-techniques\, we were 
 able to derive stability fields for Np(VI) in aqueous solutions and correl
 ate this to data derived from conventional Eh and pH measurements. Having 
 established the relevance of Np(VI) we have proceeded to perform integral 
 solubility studies in dilute to concentrated NaCl solutions over the entir
 e alkaline pH range. The studies show a distinct dependence of the Np(VI) 
 solubility on pH and ionic strength conditions and indicate significant Np
 (VI) retention over a large set of chemical boundary conditions. By analys
 ing the solubility data and comparing to the previously investigated chemi
 cally analogue U(VI) system\, we were able to derive a comprehensive therm
 odynamic model for the system Np(VI)-Na+-H+-OH--Cl--H2O at 25°C not avail
 able before.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=113
 &sessionId=30&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=113&sessionId=3
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Selective liquid-liquid extraction of Sr-85 with modified calixare
 nes
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-112@cern.ch
DESCRIPTION:Speakers: Ms. POETSCH\, Maria (Helmholtz-Zentrum Dresden-Rosse
 ndorf\, Institute of Resource Ecology\, Reactive Transport Division / Univ
 ersität Leipzig\, Germany)\, Dr. MANSEL\, Alexander (Helmholtz-Zentrum Dr
 esden-Rossendorf\, Germany)\nSr-90 is a long-lived radionuclide (T(1/2) = 
 28.6 a)\, produced as a by-product in nuclear power plants. Due to its che
 mically similarity to calcium\, it follows the food chain from environment
  (e.g. aquatic systems and soil) to fauna and human in case of release in 
 the biosphere. Strontium can be\, as well as calcium\, incorporated in bon
 es. Stable isotopes of strontium might not be harmful\, but radioactive st
 rontium can lead to bone disorders and diseases\, including leukaemia[1].\
 nCalixarenes and their functionalised derivatives are research subjects in
  the development of extracting agents\, transporters\, stationary phases[2
 ] or bio-sensors. We used modified calixarenes\, including derivatives hav
 ing carbonyl binding sites\, for the extraction of strontium[3] by means o
 f a liquid-liquid extraction in a chloroform / water system. As a simulate
 d contamination solution with Sr-90\, the aqueous strontium phase was trac
 ed using the short-lived radionuclide Sr-85 (T(1/2) = 64.9 d)\, which was 
 produced and purified at the in-house 18 MeV-cyclotron[4]. \nUnder alkalin
 e conditions\, strontium extraction yields of >(90±4)% were obtained. Fur
 thermore\, the impact of inorganic and organic impurities\, competing ions
  like sodium\, calcium\, acetate or tartaric acid\, to the extraction perf
 ormance was studied. The used carboxy-modified calixarenes are highly pote
 nt and selective extracting agents towards strontium\, under conditions ne
 ar to nature (e.g. synthetic groundwater).\n\n\n[1] Wallova\, G.\, N. Kand
 ler\, and G. Wallner\, Monitoring of radionuclides in soil and bone sample
 s from Austria. Journal of Environmental Radioactivity\, 2012. 107(0): p. 
 44-50.\n[2] Wendel\, V.\, Neuartige Wirt-Gast-Komplexe basierend auf Cyclo
 heptatrienbausteinen\, Mathematisch-Naturwissenschaftliche Fakultät I 199
 8\, Humboldt-Universität zu Berlin: Berlin.\n[3] Casnati\, A.\, et al.\, 
 New Efficient Calixarene Amide Ionophores for the Selective Removal of Str
 ontium Ion from Nuclear Waste: Synthesis\, Complexation\, and Extraction P
 roperties. J. Am. Chem. Soc.\, 2001. 123: p. 12182-12190.\n[4] Mansel\, A.
 \, et al.\, Production of Sr-85 at a 18 MeV-cyclotron and purification for
  geochemical investigations\, 2012. (submitted)\n\nhttp://indico.cern.ch/c
 ontributionDisplay.py?contribId=112&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=112&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Nuclear analytical methods in prostate cancer di
 agnostics
DTSTART;VALUE=DATE-TIME:20120919T133000Z
DTEND;VALUE=DATE-TIME:20120919T135000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-82@cern.ch
DESCRIPTION:Speakers: Dr. ZAICHICK\, Vladimir (Medical Radiological Resear
 ch Center\, Russia)\nThe contents of twelve trace elements in normal (n=37
 )\, benign hypertrophic (n=43) and cancerous tissues (n=60) of the human p
 rostate gland were investigated by instrumental neutron activation (INAA) 
 and by radionuclide-induced (109Cd) energy dispersive X-ray fluorescent (E
 DXRF) analysis. The contents of Ag\, Co\, Cr\, Fe\, Hg\, Rb\, Sb\, Sc\, Se
 \, and Zn\, and of Br\, Fe\, Rb\, Sr\, and Zn were measured by INAA and ED
 XRF\, respectively. The content of Fe\, Rb\, and Zn in samples was determi
 ned by two methods and mean values of the element mass fractions were quot
 ed as a result. Mean values (M  SΕΜ) for mass fraction (mg/kg\, dry w
 eight basis) in normal tissue were: Ag – 0.0480.009\, Br 40.65.6\,
  Co – 0.0450.004\, Cr – 0.530.08\, Fe – 1156\, Hg – 0.056
 0.011\, Rb – 14.40.9\, Sb – 0.0450.007\, Sc – 0.0290.005
 \, Se – 0.700.04\, Sr 2.50.4\, and Zn – 1078113. In our previ
 ous studies it was shown that Zn and Ca levels in prostate are almost one 
 order of magnitude higher than in other soft tissues. The obtained means f
 or Br and Cr mass fraction are more than two times higher than mean values
  of element content in skeletal muscle\, liver and whole blood. So\, the h
 uman prostate accumulates not only Zn and Ca\, but also such trace-element
 s as Br and Cr. It was observed that in benign hypertrophic tissues the co
 ntents of Co\, Cr\, Hg\, Sb\, and Se were higher and the contents of Br\, 
 Fe\, Rb\, Sr\, and Zn were equal to those in normal tissues. The contents 
 of Co\, Rb\, Sc\, and Zn were lower and those of Ag\, Br\, Cr\, Fe\, Hg\, 
 Sb and Sr were higher in cancerous tissues than in normal tissues. Finally
 \, we propose to use the in vitro and in vivo estimation of Zn mass fracti
 on in gland as an accurate tool to diagnose prostate cancer.\n\nhttp://ind
 ico.cern.ch/contributionDisplay.py?contribId=82&sessionId=25&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=82&sessionId=25
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Pu-240/Pu-239 atom ratios in the northern North Pacific and equato
 rial Pacific water columns
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-83@cern.ch
DESCRIPTION:Speakers: Prof. YAMADA\, Masatoshi (Hirosaki University\, Japa
 n)\nAnthropogenic radionuclides such as Pu-239 (half-life: 24\,110 years)\
 , Pu-240 (half-life: 6\,564 years) and Pu-241 (half-life: 14.35 years) hav
 e been released into the environment as the result of atmospheric nuclear 
 weapons testing\, disposal of nuclear wastes and nuclear fuel-cycle reproc
 essing operations\, etc. In the North Pacific Ocean\, two distinct sources
  of Pu isotopes can be identified\; i.e.\, the global stratospheric fallou
 t and close-in tropospheric fallout from nuclear weapons testing at the Pa
 cific Proving Grounds (PPG) in the Marshall Islands. The atom ratio of Pu-
 240/Pu-239 is a powerful fingerprint to identify the sources of Pu in the 
 ocean.\n  The objectives of this study are to measure the Pu-240/Pu-239 at
 om ratios in seawater from the northern North Pacific Ocean and the equato
 rial Pacific Ocean and to discuss the transport processes of Pu. \n  The P
 u-240/Pu-239 atom ratios were measured with a double-focusing SF-ICP-MS\, 
 which was equipped with a guard electrode to eliminate secondary discharge
  in the plasma and to enhance overall sensitivity.\n  In the equatorial Pa
 cific\, Pu-240/Pu-239 atom ratios were 0.215 in the surface water and incr
 eased gradually with depth reaching 0.267 at the 3000 m depth after which 
 they decreased with depth to 0.228 at the bottom layer. In the northern No
 rth Pacific\, Pu-240/Pu-239 atom ratios showed no notable variation from s
 ubsurface water of 100 m depth to deep water of 2000 m depth\, then increa
 sed with depth to 0.255 at the bottom layer. The atom ratios in water colu
 mns of the northern North Pacific and equatorial Pacific were significantl
 y higher than the mean global fallout ratio of 0.18. High atom ratios of P
 u-240/Pu-239 prove the presence of close-in tropospheric fallout from nucl
 ear weapons testing at the Pacific Proving Grounds.\n\nhttp://indico.cern.
 ch/contributionDisplay.py?contribId=83&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=83&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - On the development of a rapid method for the c
 oncentration and separation of radiostrontium from water samples based on 
 a new Sr selective resin
DTSTART;VALUE=DATE-TIME:20120920T085500Z
DTEND;VALUE=DATE-TIME:20120920T091000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-80@cern.ch
DESCRIPTION:Speakers: Dr. HAPPEL\, Steffen (TrisKem International\, Bruz\,
  France)\nDue to its radiotoxicity there is a strong need for the determin
 ation of Sr-90 in environmental samples. One of the main pathways for Sr-9
 0 ingestion is the consumption of water\; accordingly the determination of
  Sr-90 in water samples is of special importance\, in routine analysis for
  environmental monitoring as well as in emergency situations and contamina
 tion control. Rapid methods are of high interest in both of these cases\, 
 in emergency situations and contamination control\, since fast results are
  needed in order to evaluate a situation thus allowing appropriate measure
 s to be taken\, and in routine analysis as they allow fast sample turn-aro
 und time and thus high sample throughput.\nIn order to allow the quantific
 ation of Sr-90 by -spectrometry it is necessary to perform a number of 
 sample preparation steps upfront to the measurement: sample pre-treatment\
 , chemical separation and the preparation of counting samples. Sr-90 is fr
 equently concentrated from water samples using co-precipitation or ion exc
 hange methods both requiring considerable hands-on and overall lab time. \
 nSome results of the development and characterization of a new Sr selectiv
 e resin\, allowing direct concentration and separation of 90Sr from enviro
 nmental water samples are presented. A number of candidate resins were pre
 pared based on the Sr selective crown-ether di-t-butyl dicyclohexyl-18-cro
 wn-6 and varying amounts of di(2-ethyl-hexyl)phosphoric acid\, selected ro
 om temperature ionic liquids (RTILs) respectively. Best suited candidate r
 esins were identified\, and further characterised\, through batch experime
 nts. Based on obtained results a separation scheme has been developed and 
 optimized\, allowing Sr  to be successfully separated from synthetic sampl
 es.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=80&sessionId
 =27&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=80&sessionId=27
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Application of a mixed bed column for the removal of iodine from r
 adioactive process effluents
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-81@cern.ch
DESCRIPTION:Speakers: Dr. HAPPEL\, Steffen (TrisKem International\, Bruz\,
  France)\nSafety and appropriate management of nuclear waste are of major 
 importance in radioisotope production. Radioiodine has been identified as 
 one of the most dangerous radioelements in terms of radiological effects o
 n the population in case of accidental release\; accordingly substantial e
 fforts have been made to optimize the iodine capture in liquid effluents d
 uring the production process to avoid any possible iodine gas release from
  liquid waste during storage. The IRE production process results in highly
  acidic and oxidizing effluents\, iodine might thus be present in various 
 oxidation states and species. This needs to be taken into account for the 
 decontamination of these effluents\; accordingly a mixed bed column approa
 ch was chosen. \nLiterature reports the use of anion exchange resins and m
 ore recently of silver-coated sorbents such as zeolithes\, alumina or acti
 vated carbon for iodine removal\, the letter being very attractive as silv
 er is known to interact very strongly with iodine.  However\, these sorben
 ts show significant leaching of silver when used in acidic media and can t
 hus not be used in the present case. \nCL Resin (TrisKem International) is
  an extractionchromatographic resin that retains silver over a wide pH ran
 ge including high acid concentrations. It was further shown\, after being 
 loaded with silver\, to strongly retain iodine species forming insoluble c
 omplexes with silver making it well suited for use in the given context\; 
 XAD-4 Resin (Sigma) on the other hand is known to retain elemental iodine.
  \nA mixed bed column based on silver loaded CL Resin and XAD-4 resin was 
 developed and optimized for iodine removal from IRE’s process effluents 
 by varying column size and resin ratios. Prepared mixed bed columns were e
 valuated by treating multi-curies production process solutions at the IRE.
  The mixed bed columns showed high iodine removal from elevated effluent v
 olumes (> 10 L) even at flow-rates up to 150 mL/min.\n\nhttp://indico.cern
 .ch/contributionDisplay.py?contribId=81&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=81&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Nuclear spallation reactions in chromium\, yttrium and terbium wit
 h 386 MeV neutrons
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-119@cern.ch
DESCRIPTION:Speakers: Dr. SEKIMOTO\, Shun (Kyoto University Research React
 or Institute\, Japan)\nNeutron-induced reaction cross sections serve as a 
 comprehensive nuclear database for estimating residual radioactivities in 
 accelerator facilities.  These data are also important in the field of cos
 mochemistry for deciphering the cosmic-ray irradiation history.  However\,
  neutron cross sections in the energy range above 100 MeV have scarcely be
 en measured experimentally except for those from few targets\; C\, Cu\, Pb
 \, Bi and so on.  Those obtained from calculation codes are utilized and p
 roton cross section data are also utilized on the basis of the assumption 
 that neutron cross sections in higher energies than 100 MeV approximately 
 equal to proton ones in the same energy range.\nIn this work\, we measured
  reaction cross sections of radionuclides produced through nuclear spallat
 ion reaction from Cr\, Y and Tb induced by neutrons at 386 MeV\, which hav
 e never been reported.  The irradiations were carried out using neutrons p
 roduced through Li-7 (p\, n) reaction at N0 beam line in the Research Cent
 er for Nuclear Physics (RCNP)\, Osaka University.  To estimate quasi-monoe
 nergetic neutron induced cross sections\, the target stacks of Cr\, Y and 
 Tb were irradiated on the two angles of 0 and 25 degrees for the axis of t
 he primary proton beam.  The yields of the spallation products were measur
 ed by gamma-ray spectrometry.  Neutron cross sections were estimated by su
 btracting the yields produced in the samples placed on 25 degree from thos
 e of 0 degree to correct the contribution of the low energy tail in the ne
 utron spectrum.  The results obtained in this work will be compared to the
  cross section data for the same target materials with 287 MeV neutrons in
  our previous work.  Since proton-induced cross sections for the same targ
 ets in the same energy range are also measured\, neutron cross sections ob
 tained can be compared to the proton ones.\n\nhttp://indico.cern.ch/contri
 butionDisplay.py?contribId=119&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=119&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Experiments to demonstrate chemical containment: Solubility under 
 the cementitious conditions of a repository in the UK
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-87@cern.ch
DESCRIPTION:Speakers: Dr. FELIPE-SOTELO\, Monica (Loughborough University\
 , UK)\nOne option for the long-term management of intermediate level radio
 active wastes is deep geological disposal. The waste is grouted with cemen
 t in steel canisters for disposal\; after closure\, the repository may be 
 backfilled with more cement. The cement porewater is expected to be of hig
 h pH due to cement dissolution and low Eh due to canister corrosion. This 
 work describes a series of long term experiments to demonstrate precipitat
 ion and solubility limitation under these conditions. \nThe experiments ar
 e expected to last 4 years and interim results are presented here. The ele
 ments included are Cs\, Ni\, Eu\, U and Th\, I as iodide and Se\, as SeO32
 -. Four solutions are being tested\, NaOH\, saturated Ca(OH)2\, NRVB (a li
 mestone-rich backfill) -equilibrated water and cellulose degradation produ
 cts (CDP) in NRVB. Additional experiments in CDP are being carried out in 
 the presence of reducing agents (metallic Fe and Na2S2O4). Solubility is a
 ssessed from both under- and oversaturation directions. \nAfter one year o
 f periodic sampling\, steady state has been reached for U and Ni. Ca(OH)2 
 is a good surrogate for the behaviour of radionuclides in NRVB\, showing s
 imilar results to the reference backfill. CDP increase the solubility of N
 i and U by several orders of magnitude\, whereas Th and Eu are less affect
 ed. The solubility of Se is clearly conditioned by the availability of Ca 
 in solution\, and there is no evidence of a decrease in the concentration 
 of Cs or I by co-precipitation. XRD analyses of precipitated solids show p
 oorly crystalline phases in the oversaturation experiments. Only incipient
  crystallinity was observed for undersaturation\, which could explain the 
 differences observed in measured solubility between the two sets of experi
 ments.\nAcknowledgments: The authors would like to thank NDA for funding t
 his project\, Dr S. Williams (NDA) for his advice\, Dr C. Kirk (Loughborou
 gh University) for her expertise in XRD and Dr A. Milodowski (BGS) for tec
 hnical support and helpful discussions.\n\nhttp://indico.cern.ch/contribut
 ionDisplay.py?contribId=87&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=87&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Fractionation of U\, Th\, Ra and Pb from boreal forest soils by se
 quential extractions
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-84@cern.ch
DESCRIPTION:Speakers: Ms. VIRTANEN\, Sinikka (University of Helsinki\, Fin
 land)\nTo study the mobility of the natural radionuclides in forest soil a
  five step sequential extraction procedure was carried out to soil samples
  taken from various depths down to three meters at the Olkiluoto Island\, 
 Finland\, where the final disposal repository of spent nuclear fuel is pla
 nned to be constructed in the bedrock. The studied extraction fractions we
 re exchangeable\, acid-soluble\, reducible\, oxidizable and tightly bound.
  It was found that the extractability of most of the studied radionuclides
  was dependent on the sample grain size and depth. All the elements were f
 ound to be concentrated in the smallest grain size samples (\n\nhttp://ind
 ico.cern.ch/contributionDisplay.py?contribId=84&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=84&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Separation of carrier free 177Lu from 177Lu /Yb mixture by electro
 -amalgamation of ytterbium
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-85@cern.ch
DESCRIPTION:Speakers: Dr. CIESZYKOWSKA\, Izabela (National Centre for Nucl
 ear Research\, Radioisotope Centre POLATOM\, Poland)\nThe process of isola
 tion of no-carrier added 177Lu produced via 176Yb(n\,gamma)177Yb - 177Lu f
 rom mixture containing macroscopic amounts of the ytterbium target materia
 l was investigated. For this purpose a novel method of electrochemical sel
 ective amalgamation of ytterbium from 177Lu/Yb mixture into mercury-pool c
 athode was applied. The electrolyte solution contained mixture of 20 mg yt
 terbium in 5M HCl and 177Lu as 177LuCl3  in 0.15 M sodium citrate. As anod
 e platinum plate was used. In order to develop an optimal condition of ama
 lgamation of ytterbium\, effects of pH of the electrolyte solution\, poten
 tial and time of the electrochemical process as well as number of cycle of
  electrolysis performed under the same conditions using fresh electrodes w
 ere examined. The concentration of lutetium and ytterbium in the electroly
 te solution was determined by spectrometry ICP-OES. The best performance o
 f the method\,  allowing cementation up to 94 % of ytterbium from the 177L
 u/Yb mixture was obtained at pH of 6-7\, potential of 8 V\, time of 60 min
  and two cycles of the electrolysis. Concentration of 177Lu in the solutio
 n after fixing ytterbium in amalgam remained at the same level. As results
  of such defines process molar ratio of Yb:Lu was reduced from 3000 to 170
 . The atomic absorption spectroscopy (AAS) measurement showed that the con
 tent of mercury in the solution containing 177Lu after cementation of the 
 ytterbium was bellow detection and determination limit  level amounted res
 pectively 0.3 and 0.6 µg/kg.\n\nhttp://indico.cern.ch/contributionDisplay
 .py?contribId=85&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=85&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - RIKEN GARIS as a promising interface for super
 heavy element chemistry –Production of 261Rf\, 262Db\, and 265Sg for che
 mical studies using the GARIS gas-jet system–
DTSTART;VALUE=DATE-TIME:20120918T091000Z
DTEND;VALUE=DATE-TIME:20120918T092500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-207@cern.ch
DESCRIPTION:Speakers: Dr. HABA\, Hiromitsu (RIKEN\, Japan)\nChemical chara
 cterization of superheavy elements (SHEs\, atomic numbers Z ≥ 104) is an
  extremely interesting and challenging subject in modern nuclear and radio
 chemistry. We have been developing a gas-jet transport system coupled to t
 he RIKEN gas-filled recoil ion separator GARIS as a novel technique for SH
 E chemistry. This system is a promising approach for exploring new frontie
 rs in SHE chemistry: (i) the background radioactivities of unwanted reacti
 on products are strongly suppressed\, (ii) the intense beam is absent in t
 he gas-jet chamber and hence high gas-jet transport efficiency is achieved
 \, and (iii) the beam-free condition also allows for investigations of new
  chemical systems. In this work\, we investigated the performance of the s
 ystem using 261Rf (Z = 104)\, 262Db (Z = 105)\, and 265Sg (Z = 106) produc
 ed in the 248Cm(18O\,5n)261Rf\, 248Cm(19F\,5n)262Db\, and 248Cm(22Ne\,5n)2
 65Sg reactions\, respectively. The evaporation residues of interest were f
 irst separated in flight from the beam and the majority of the nuclear tra
 nsfer products by GARIS and were guided to the gas-jet chamber at the foca
 l plane of GARIS. The evaporation residues were thermalized in helium gas 
 in the gas-jet chamber\, were attached to KCl aerosol particles\, and were
  transported through a Teflon capillary to a chemistry laboratory. Alpha a
 nd spontaneous fission decays of 261Rfa\,b\, 262Db\, and 265Sga\,b were th
 en investigated with the rotating wheel apparatus MANON under extremely lo
 w background conditions. In the conference\, productions and decay propert
 ies of those nuclides will be discussed in detail. A chemistry program usi
 ng the GARIS gas-jet system will be also presented.\n\nhttp://indico.cern.
 ch/contributionDisplay.py?contribId=207&sessionId=20&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=207&sessionId=2
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Prompt Gamma Activation Analysis close to Dete
 ction Limits
DTSTART;VALUE=DATE-TIME:20120920T081000Z
DTEND;VALUE=DATE-TIME:20120920T082500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-173@cern.ch
DESCRIPTION:Speakers: Dr. KUDEJOVA\, Petra (Technische Universitaet Muench
 en\, Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II)\, Garching\, 
 Germany)\nThe ultimate detection limits (DL) of the Prompt Gamma Activatio
 n Analysis (PGAA) method depend strongly on the amount and matrix of the m
 easured sample as well as on the background signal contribution to the sig
 nal coming from the sample itself.\n\nRecently\, we have performed few exp
 eriments close to the detection limits for given elements at the high-flux
 -PGAA facility at FRM II in Garching. One of the most important element wh
 ich can be determined by the PGAA technique  is Hydrogen. Hydrogen impurit
 ies in Silicon as well as Hydrogen implantation in Beryllium crystals were
  measured and analysed. Concerning Silicon\, which appears frequently in t
 he nature and so in the PGAA samples\, we could determine 3 ppm Hydrogen i
 n the crystals. However\, the constrain appeared to be the Hydrogen from t
 he surrounding materials (which cannot be avoided) and we estimate its sig
 nal being comparable to a concentration of about 1 ppm. \nThe Hydrogen imp
 lantation to Beryllium crystal was measured by slightly different conditio
 ns to lower the Hydrogen contribution from the surroundings of the sample.
  The analysis is still in progress and exact values will be known soon.\n\
 nAnother experiment testing the limits of the PGAA facility at FRM II was 
 performed in a frame of a Transmutation detectors (TMD) proposal. TMD's ar
 e small high‑purity metallic foils or single crystal samples\, irradiate
 d close to the reactor core at any research or power reactor for a long ti
 me (even months). To calculate the neutron flux as well as fluence at the 
 position\, not the activity of the detectors after long‑term irradiation
  is analysed\, but the concentration of transmuted isotopes with appropria
 te neutron capture cross‑section. The main advantage of this method is t
 he independence of the time parameter: the information is "stamped" to the
  samples and can be read any time later. The samples irradiated for 21 day
 s at the LWR-15 in Rez\, Czech Republic\, were pure natural Copper\, Alumi
 num and Gold\, the searched isotopes were 59-Ni and 63-Ni in Ni foil\, 64-
 Ni in Cu foil\, 198-Hg and 199-Hg in Au foil [ref.1]\nIn this presentation
 \, the experiments and the results will be discussed and possible ways how
  to improve the detection limits will be proposed.\n\n[1] L. Viererbl et a
 l.\, Nucl. Instum. Meth. A 632 (2011) 209.\n\nhttp://indico.cern.ch/contri
 butionDisplay.py?contribId=173&sessionId=27&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=173&sessionId=2
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Time lag between the tropopause height and <sup>7</sup>Be activity
  concentrations on surface air
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-226@cern.ch
DESCRIPTION:Speakers: Prof. IOANNIDOU\, Alexandra (Aristotle University of
  Thessaloniki\, Physics Department\, Nuclear Physics & Elementary Particle
  Physics Division\,  Thessaloniki 54124\, Greece)\nThe objective of this s
 tudy is to define the time-lag between the elevation of tropopause and the
  concentration of 7Be in near surface air. The concentration of 7Be at sur
 face air has been determined in the region of Thessaloniki\, Greece at 40
 °N\, over 52 weekly measurements covering the year 2009\, a year of a dee
 p solar minimum and of maximum concentration of 7Be\, where any fluctuatio
 n due to meteorological and seasonal variations are easily revealed. \n	Sa
 mpling of 7Be aerosols was carried out by Staplex high-volume air sampler 
 with glass-fiber filters\, and a regulated airflow rate of 1.7-1.92 m3 min
 -1 (60-68 ft3 min-1). The length of each collection period was 24 h. All s
 amples were measured for 7Be activity using an HPGe detector (42% relative
  efficiency). The tropopause height time series of daily values was obtain
 ed from the NCEP/NCAR Reanalysis data. \n	The positive correlations betwee
 n the monthly activity concentrations of 7Be and the tropopause height (0.
 94\, p\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=226&sessi
 onId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=226&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Experimental Performance Evaluation of a Compton Suppression Syste
 m for Neutron Activation Analysis by Using a Gamma-ray Source and Standard
  Reference Materials
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-172@cern.ch
DESCRIPTION:Speakers: Mr. MOON\, JongHwa (Korea Atomic Energy Research Ins
 titute\, Korea)\nA Compton suppression system (CSS) was implemented at a n
 eutron activation analysis laboratory of the Korea Atomic Energy Research 
 Institute (KAERI) in 2009 and its performance was evaluated experimentally
  by the measurement of a gamma-ray emitting source and of detectable nucli
 des created by neutron activation with the NIST standard reference materia
 ls (SRMs). Four geological and five biological SRMs were chosen and irradi
 ated by using an NAA#1 irradiation hole at the HANARO research reactor. A 
 gamma-ray spectrum with normal mode and anti-coincidence mode were acquire
 d at the same time\, and advantage factors of CSS for each nuclide detecte
 d were calculated on the basis of signal-to-noise ratio. 531 keV of Nd-147
  shows the highest advantage factor\, 3.30\, from geological samples\, and
  559 keV of As-76 shows the highest advantage factor\, 2.36\, from biologi
 cal samples. The mean AF values for the nuclides detected from four geolog
 ical and five biological SRMs were 1.99 and 1.63\, respectively.\n\nhttp:/
 /indico.cern.ch/contributionDisplay.py?contribId=172&sessionId=26&confId=1
 83405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=172&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Analysis of Radioactive Waste Waters and Sludg
 es int he Hungarian VVER NPP Paks
DTSTART;VALUE=DATE-TIME:20120920T074000Z
DTEND;VALUE=DATE-TIME:20120920T075500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-177@cern.ch
DESCRIPTION:Speakers: Prof. PÁTZAY\, György (BME KKFT\, Hungary)\nThere 
 are some tanks at the nuclear power plant in Paks\, Hungary containing slu
 dge type radioactive waste containing more or less liquid phase too. The g
 eneral physical and chemical charactersitics (density\, pH\, total solid\,
  dissolved solid etc.) and chemical and radiochemical composition of these
  sludges are important information for volume reduction and solidification
  treatment of theese wastes. Based on the literature sources we have inves
 tigated and constructed a complex analysis system for the radioactive slud
 ge and supernatant analysis\, including the physical\, as well as the chem
 ical and radiochemical analysis methods. Using well known analysis techniq
 ues as ion chromatography\, ICP-MS\, AAS\, gamma-and alfa-spectrometry and
  chemical alkaline fusion digestion and acidic dissolution methods we coul
 d analyze the main inorganic\, organic and radioactive components of the s
 ludges and supernatants. Determination of the mass and charge balance for 
 the sludge samples were more difficult then for the supernantant samples. 
 Not only are there assumptions required about the chemical form and the ox
 idation state of the species present in the sludge\, but many of the compo
 unds in the sludge are mixed oxides which are not directly measured. Also\
 , the sludge is actually a slurry with a high water content. The interstit
 ial liquid is in close contact with the sludge\, and there are many ionic 
 solubility equilibriums. The anion data for the sludge samples are based o
 n the water soluble anions that would be available to a water wash. The wa
 ter wash would not account for the insoluble hydroxides\, carbonates\, and
  mixed oxides present. The insoluble species do not contribute to the char
 ge balance\, and the cation charge is not used in the calculation. Most of
  the nitrate reported for the sludge is due to the interstitial liquid. Co
 nsidering the limitations of these calculations\, the mass balance was wit
 hin the analytical error (±20%) for the sludge samples. There were three 
 sample preparation methods used to investigate the total anion content of 
 the sludge samples\, which included water leach\, potassium-hydroxide and/
 or sodium peroxide/sodium hydroxide fusion and acidic dissolution.\n\nhttp
 ://indico.cern.ch/contributionDisplay.py?contribId=177&sessionId=27&confId
 =183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=177&sessionId=2
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Radionuclides and radiopharmaceuticals at POLATO
 M
DTSTART;VALUE=DATE-TIME:20120919T073000Z
DTEND;VALUE=DATE-TIME:20120919T075000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-254@cern.ch
DESCRIPTION:Speakers: Dr. MIKOLAJCZAK\, Renata (NCBJ Radioisotope Centre P
 OLATOM\, Poland)\nRadioisotope Centre POLATOM is a state owned laboratory 
 in the structure of the National Centre for Nuclear Research. POLATOM deve
 lops techniques for practical application of radioisotopes in various sect
 ors\, among them majority of products and services used in health care. PO
 LATOM is supporting domestic and international users in highly specialized
  radiopharmaceuticals and radiochemicals for nuclear medicine and related 
 fields\, among them a number of products utilizing radionuclides irradiate
 d in the multifunctional MARIA Research Reactor. POLATOM’s facilities ar
 e well equipped and certified for manufacturing of radiopharmaceuticals. W
 e are also carrying out extensive research programs on the new development
 s in the application of radionuclides supported by national and internatio
 nal multidisciplinary collaborations.\nThe main research and development d
 omains are:\n1.	Investigation of novel biomolecules as carriers for radion
 uclides and preliminary assessment of their diagnostic and/or therapeutic 
 utility. \n2.	Development of technologies for the production of high speci
 fic activity radionuclides in nuclear reactors and accelerators\, using hi
 ghly enriched target materials and modern separation techniques.\n3.	Devel
 opment of methods for radioactivity measurement and assessment of radionuc
 lidic purity (determination of \, β\, and  impurities).\n4.	Chemica
 l and pharmaceutical development as well as in vitro and in vivo assessmen
 t of biological activity of new radiopharmaceuticals for clinical applicat
 ions. \nA very good communication network with domestic nuclear medicine u
 nits and research institutes interested in radiopharmaceutical development
  as well as with several international research institutions has been deve
 loped\, supported by scientific and applied grants. The Centre participate
 s in research projects coordinated by the International Atomic Energy Agen
 cy (IAEA) as well as in the European cooperation program of scientific and
  technical cooperation COST.\n\nhttp://indico.cern.ch/contributionDisplay.
 py?contribId=254&sessionId=23&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=254&sessionId=2
 3&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - New experiments to study properties of <sup>26
 8</sup>Db produced in the <sup>48</sup>Ca + <sup>243</sup>Am reaction
DTSTART;VALUE=DATE-TIME:20120918T082500Z
DTEND;VALUE=DATE-TIME:20120918T084000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-146@cern.ch
DESCRIPTION:Speakers: Dr. AKSENOV\, Nikolay (Flerov Laboratory of Nuclear 
 Reactions\, Joint Institute for Nuclear Research\, Russia)\nWe conducted a
  new round of experiments to isolate and study chemical properties of 268D
 b\, the end product of 288115 synthesized in a 48Ca + 243Am reaction. In c
 ontrast to previous experiments [1\, 2] the reaction products passed throu
 gh a gas filled recoil separator (DGFRS) and were stopped in a catcher (co
 pper foil) which provided an additional separation from the actinides with
  a decontamination factor of 4 – 5 orders of magnitude. The chemical sep
 aration procedures have been developed for selective isolation of Db from 
 the catcher using coprecipitation with LaF3 [3]\, ion-exchange and extract
 ion chromatography from HF and HCl solutions. Altogether 8 spontaneous fis
 sion events were detected with a half-life of 23+13-6 hour. The cross-sect
 ion for the production of 288115 was found to be 6+3.6-2.4 pb. This is in 
 agreement with the previously reported data [1\, 2\, 4]. According to all 
 previous experiments the half-life of spontaneously decaying nuclide 268Db
  was estimated to be 27.4+4.6-3.4 hour. Also the extraction behavior of Db
  together with those of the lighter group-5 elements Nb and Ta into UTEVA 
 resin was investigated in 2 – 5.5 M HCl solutions by reversed-phase extr
 action chromatography. The obtained order of extraction Nb > Ta > Db sugge
 sts that stability of the chloride complex of Db is lower than those of Nb
  and Ta.\nThe work was supported by Russian Foundation for Fundamental Res
 earch (project code 11-03-12058-ofi-m).\n[1] S.N. Dmitriev et al.\, Mendel
 eev Communications 15\, 1\, 1 (2005).\n[2] N.J. Stoyer et al.\, Nuclear Ph
 ysics A 787\, 388-395 (2007).\n[3] N.V. Aksenov et al.\, Phys. Part. Nucle
 i Letters 8\, 4\, 356-363 (2011).\n[4] Yu.Ts. Oganessian et al. Phys. Rev.
  Lett. 108\, 022502 (2012).\n\nhttp://indico.cern.ch/contributionDisplay.p
 y?contribId=146&sessionId=20&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=146&sessionId=2
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - Organic PET-Radiopharmaceuticals – Aspects of 
 Previous and Current Labelling Techniques
DTSTART;VALUE=DATE-TIME:20120917T120000Z
DTEND;VALUE=DATE-TIME:20120917T122000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-255@cern.ch
DESCRIPTION:Speakers: Prof. STEINBACH\, Jörg (Helmholtz-Zentrum Dresden-R
 ossendorf\, Germany)\nDiagnostic radiopharmacy has a long-term development
  since the early investigations of G. v. Hevesy/ F. A. Paneth and the rout
 ine availability of radionuclides. After the age of gamma-emitting radioph
 armaceuticals\, which are still the working horses of nuclear medicine\, i
 n the late seventies a new radiochemical/radiopharmaceutical progression s
 tarted: The era of Positron Emission Tomography (PET) accompanied by the d
 evelopment of PET-scanners and related reconstruction- and processing-algo
 rithms.   \nMeanwhile PET is an established routine method – starting wi
 th few PET-Centres worldwide coming to a broad application in many countri
 es of the world. This growth was accompanied by various influences to basi
 c labelling techniques. \nWhat are the trends in (PET-) radiopharmaceutica
 ls/labelling techniques? \n- For routine use automatable\, simple one- or 
 two-step synthesis are preferred\n- A continuous increase of activity leve
 l in routine production takes place\n- Development of targetry for improve
 d yields and radiochemical purity\n- Aspects of pharmaceutical production 
 rule the daily life for routine PET (GMP)\n- Search for new and simple lab
 elling methods\n- Search for highly specific radiotracers \n- Introduction
  of positron emitting metallic radionuclides with medium half life\n- Comb
 ining therapeutic and diagnostic isotope pairs for therapy and dose estima
 tion\n\nThese developments are  pushed on by applying PET not only for fun
 ctional diagnostics but also by follow up diagnostics\, the need for quant
 ification of physiological parameters and the acceleration of drug applica
 tion. \nIn addition\, radiochemists are aiming at further evolvement of ne
 w labelling techniques based on the progress in – primarily – organic 
 chemistry. Such synthetic pathways have to be simplified\, downgraded and 
 speeded up mainly driven by the short half-life of the radionuclides appli
 ed. That needs a high level of automation and low substance amounts to be 
 handled. \n\nThe presentation will cover these topics from the radiopharma
 ceutical point of view.\n\nhttp://indico.cern.ch/contributionDisplay.py?co
 ntribId=255&sessionId=17&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=255&sessionId=1
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - The Road to Cyclotron Produced Tc-99m
DTSTART;VALUE=DATE-TIME:20120919T090000Z
DTEND;VALUE=DATE-TIME:20120919T092000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-245@cern.ch
DESCRIPTION:Speakers: Prof. MCQUARRIE\, Steve (University of Alberta\, Can
 ada)\nResearchers at the University of Alberta have demonstrated that it i
 s possible to produce and extract clinically significant quantities of 99m
 Tc via the 100Mo(p\,2n)99mTc nuclear reaction. Cyclotron targets have been
  engineered which significantly enhance their power-handling capacity to a
 llow for extended high current irradiation.  In addition\, a process has b
 een developed which allows for the efficient dissolution of the cyclotron 
 target substrate\, separation of the 99mTc and unreacted 100Mo and recover
 y of the expensive 100Mo for recycling.  The quality of the extracted 99mT
 c has been verified by appropriate quality control protocols and animal bi
 odistribution studies were performed which culminated in the completion of
  the first human clinical trial comparing with cyclotron produced 99mTc wi
 th reactor produced 99Mo/99mTc. Details will be presented on each of the s
 teps in this process that highlight our solutions to the major problems th
 at were overcome to produce a reliable alternative source for this key med
 ical radionuclide.\nAcknowledgements: Our partners at the Centre Hospitali
 er Universitaire de Sherbrooke (CHUS) and Advanced Cyclotron Systems Inc. 
 We also a gratefully acknowledge financial support from NSERC/CIHR (MIS 10
 0934)\, the Non-reactor based Isotope Supply Contribution Program (NISP) o
 f Natural Resources Canada\, Alberta Cancer Foundation\, Western Economic 
 Diversification Canada and the Western Economic Partnership Agreement.\n\n
 http://indico.cern.ch/contributionDisplay.py?contribId=245&sessionId=24&co
 nfId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=245&sessionId=2
 4&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Detecting and evaluating minimal traces of radio
 isotopes in environment and foods
DTSTART;VALUE=DATE-TIME:20120921T102000Z
DTEND;VALUE=DATE-TIME:20120921T104000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-244@cern.ch
DESCRIPTION:Speakers: Prof. RANDACCIO\, Paolo (University of Cagliari\, It
 aly)\nThe radioactivity analysis often requires a very high sensitivity to
  detect minute traces of both natural and artificial radioisotopes. In man
 y cases\, to obtain the required sensitivity is necessary to carry out a c
 oncentration of the element to be determined. The measurement of the activ
 ity can be done by the alpha or gamma spectrometry according to the type o
 f emission of the radioisotope to be determined. Nowdays are frequently re
 quested results about the concentration of uranium in foods and drinkable 
 water\, the contamination by DU in the environment and humans\, the concen
 tration of artificial radionuclides in the environment as a result of atmo
 spheric nuclear explosions and nuclear accidents. This kind of analysis re
 quires the adoption of sophisticated techniques to obtain a reliable resul
 t.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=244&sessionId
 =31&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=244&sessionId=3
 1&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - A Bridge not too Far: Personalized Medicine with
  the use of Theragnostic Radiopharmaceuticals
DTSTART;VALUE=DATE-TIME:20120917T083000Z
DTEND;VALUE=DATE-TIME:20120917T090000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-247@cern.ch
DESCRIPTION:Speakers: Prof. SRIVASTAVA\, Suresh (Brookhaven National Labor
 atory\, USA)\nA major advantage of radionuclides is that they emit radiati
 on of different radiobiological effectiveness and range of action. This of
 fers the possibility of choosing a nuclide the physical and nuclear charac
 teristics of which are matched with a particular tumor type\, or the disea
 se under treatment. This presentation introduces a relatively novel paradi
 gm that involves specific individual radionuclides or radionuclide pairs t
 hat have emissions that allow pre-therapy low-dose imaging plus higher-dos
 e therapy in the same patient. We have made an attempt to sort out and org
 anize a number of such dual-purpose theragnostic radionuclides and radionu
 clide pairs that offer this exciting potential of low-dose imaging followe
 d by higher-dose treatment and  thus possibly bringing us a major step clo
 ser to personalized medicine. This approach would empower the age-long dre
 am of performing individualized or tailored radionuclide therapy in cancer
  patients\, as well as in the treatment of many other disorders that respo
 nd to radionuclide therapy. However\, an increased and reliable availabili
 ty of theragnostic radionuclides remains a major issue\, which must be add
 ressed before we can successfully put this paradigm into routine clinical 
 practice. A low-dose administration using radiopharmaceuticals based on th
 ese theragnostic radionuclides or radionuclide pairs would initially allow
  molecular imaging (SPECT/CT or PET/CT) to provide the necessary pre-thera
 py information on biodistribution\, dosimetry\, the limiting or critical o
 rgan or tissue\, and the maximum tolerated dose (MTD)\, etc.  If the imagi
 ng results then warrant it\, it would be safe and appropriate to follow up
  with dose ranging experiments to allow higher-dose targeted molecular the
 rapy with the greatest effectiveness. It is worth emphasizig that our nucl
 ear medicine modality is the only modality that can fulfill the dream of c
 arrying out tailored personalized medicine by way of enabling diagnosis fo
 llowed by therapy in the same patient with the same radiopharmaceutical. A
 t BNL\, our work on radionuclide therapy has for some time focused on the 
 development of this paradigm for application to several distinct clinical 
 areas\, e.g.\, palliation of bone pain from osseous metastases\, treatment
  of metastatic bone disease\, radiation synovectomy\, radioimmunotherapy\,
  and cardiovascular applications. This presentation will include the  disc
 ussion of a number of  individual radionuclides and radionuclide pairs whi
 ch would be potentially excellent choices for theragnostic applications. S
 ince the overall story (including preliminary clinical trials) is a bit mo
 re complete in the case of tin-117m\,  a conversion electron emitter with 
 great theragnostic potential\, it will be discussed in more detail\, as an
  example.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=247&se
 ssionId=15&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=247&sessionId=1
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - The use of nuclear analytical techniques in the 
 identification and investigation of metal- and metalloid-containing protei
 ns
DTSTART;VALUE=DATE-TIME:20120919T135000Z
DTEND;VALUE=DATE-TIME:20120919T141000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-246@cern.ch
DESCRIPTION:Speakers: Prof. BEHNE\, Dietrich (Helmholtz Centre Berlin\, Ge
 rmany)\nMost metals and metalloids present in biological materials are bou
 nd to proteins where they have essential tasks as part of the catalytic ce
 nters of enzymes or as structural components. It has been estimated that i
 n the biosphere a multitude of these compounds exists but so far relativel
 y few of them have been detected. Since in most cases the presence of a me
 tal or metalloid in a protein cannot be recognized from its genetic code\,
  specific methods for the identification of novel metal- and metallo-conta
 ining proteins and the investigation of their characteristics have to be a
 pplied. The information obtained in this way helps elucidate the biologica
 l functions of trace elements and is thus of great interest in many fields
  of the life sciences. \n\nAs the properties of most of these compounds ar
 e not yet known\, initial information on their presence in tissues or cell
 s can only be obtained by protein separation and determination of the elem
 ent contents in the isolated fractions. For these investigations gel elect
 rophoretic separation procedures have been combined with radiotracer techn
 iques and nuclear analytical methods which allow surface scanning such as 
 proton-induced X-ray emission or synchrotron radiation X-ray fluorescence.
  In the analysis of several trace elements in purified proteins or protein
  subunits\, which are usually isolated in only very small amounts\, neutro
 n activation analysis has been successfully applied. The identification of
  a novel metalloprotein is then achieved by analysis of the amino acid seq
 uence of the purified protein using MALDI-MS of the peptide fragments\, mR
 NA determination and cDNA synthesis. In this overview the applications of 
 nuclear analytical methods in this field of research and their advantages 
 and disadvantages are discussed with the help of some examples.\n\nhttp://
 indico.cern.ch/contributionDisplay.py?contribId=246&sessionId=25&confId=18
 3405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=246&sessionId=2
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Spectroscopic methods for the heaviest nuclei
DTSTART;VALUE=DATE-TIME:20120918T063000Z
DTEND;VALUE=DATE-TIME:20120918T070000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-241@cern.ch
DESCRIPTION:Speakers: Prof. HERZBERG\, Rolf-Dietmar (University of Liverpo
 ol\, UK)\nA growing number of experiments is currently opening up the tran
 sfermium region of nuclei for detailed spectroscopic investigations [1\,2]
 .  In the deformed nuclei in the nobelium region this allows an identifica
 tion and mapping of single particle orbitals closest to the top end of the
  nuclear chart.\n\n	Initial in-beam measurements in the region focussed on
  γ-ray spectroscopy of even-even nuclei (e.g. 252\,254-No\, 250-Fm)\, stu
 dying the ground-state yrast bands and allowing extraction of parameters s
 uch as the moments of inertia\, and proving the deformed nature of these n
 uclei. More recently\, attention has switched to odd-mass nuclei such as 2
 53-No\, 251-Md and 255-Lr\, the latter being the heaviest nucleus so far s
 tudied in-beam. Rotational bands have been observed in all these nuclei. N
 on-yrast and K-isomeric states have recently been observed in 252\,254-No 
 and 250-Fm through the use of both in-beam and focal plane decay spectrosc
 opy. The studies employed a calorimetric technique\, whereby the summed en
 ergy from a cascade of conversion electrons is detected in a DSSSD detecto
 r and used as a “tag” for γ-rays detected in the various germanium de
 tectors. These experiments have yielded data which can be used to determin
 e the excitation energies and configurations of two-quasiparticle states i
 n the region\, and compared to the predictions of various theories. \n\n	A
 n overview of the most recent results and the experimental techniques used
  will be presented and new experimental developments such as the SAGE spec
 trometer in Jyväskylä and the new TASISpec setup at will be discussed.\n
 \n\nThis work is supported by the UK STFC.\n\n[1] R-D Herzberg\, J. Phys. 
 G 30\, R123 (2004). \n[2] R.-D. Herzberg\, P.T. Greenlees\, Prog. Part. Nu
 cl. Phys. 61\, 674 (2008).\n\nhttp://indico.cern.ch/contributionDisplay.py
 ?contribId=241&sessionId=20&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=241&sessionId=2
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Reactor production of radionuclides for molecula
 r imaging and targeted radiotherapy
DTSTART;VALUE=DATE-TIME:20120919T075000Z
DTEND;VALUE=DATE-TIME:20120919T081000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-240@cern.ch
DESCRIPTION:Speakers: Dr. CUTLER\, Cathy (University of Missouri\, USA)\nT
 he University of Missouri Research Reactor Center (MURR) was instrumental 
 in the development of two commercialized radiotherapeutic agents:  Sm-153 
 [Quadramet] for the palliation of pain due to metastatic bone cancer\, 
 and Y-90 labeled glass microspheres [Therasphere] for the treatment of 
 liver cancer.  MURR is now actively developing other radionuclides with po
 tential for use as targeted radiotherapy of cancer.  One approach focuses 
 on attaching a radionuclide via a bifunctional chelator to a selective tar
 geting biomolecule such as a peptide or an antibody.  A second approach is
  the use of nanoparticles in which the nanoparticle is comprised of the ra
 dionuclide and allows for the delivery of multiple radionuclides per targe
 ting moiety.  Radionuclides for therapy have unique half-lives (dose rates
 ) and beta energies (tissue penetration ranges) and in addition some have 
 a low abundance of gamma emissions that allow for imaging and tracking dos
 imetry.  Radiotherapy with the new targeting moieties requires a diverse l
 ibrary of radionuclides to meet their specific needs.  For instance\, radi
 olabeled peptides\, antibodies and nanoparticles have shown promise for di
 agnosis and radiotherapy of cancer by targeting receptors over-expressed o
 n tumor cells.  Due to the low concentration of tumor-associated antigens\
 , high specific activity radionuclides and/or novel nanoparticle complexin
 g techniques are required.  Current efforts at MURR have focused on develo
 ping high specific activity radioisotopes that can be attached to biomolec
 ules\, readily converted into nanoparticles and or incorporated onto nanop
 articles and are taken up selectively by diseased tissues\; they deliver r
 adioactivity for diagnosis or treatment of disease selectively and minimiz
 e or spare damage to healthy or normal cells. These tumor targeting biomol
 ecules can be radiolabeled with different radioisotopes tailored to treat 
 different cancers and diverse patient needs.  The reactor production of ra
 dionuclides and their incorporation into nanoparticles and biomolecules wi
 ll be discussed in the context of their physical and chemical properties a
 s related to their potential utility in medical research.\n\nhttp://indico
 .cern.ch/contributionDisplay.py?contribId=240&sessionId=23&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=240&sessionId=2
 3&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Radionuclide production studies by heavy ion bea
 ms
DTSTART;VALUE=DATE-TIME:20120919T065000Z
DTEND;VALUE=DATE-TIME:20120919T071000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-243@cern.ch
DESCRIPTION:Speakers: Prof. LAHIRI\, Susanta (Saha Institute of Nuclear Ph
 ysics\, India)\n`In last two decades our research group is involved in the
  heavy ion assisted production and separation of neutron deficient no-carr
 ier-added radionuclides. The advantage of heavy ion assisted production is
  choice of wide range of projectiles and therefore increasing the possibil
 ities of reaching desired radionuclide far from the stability line. The ma
 in disadvantage is low production cross section\, which made heavy ion ass
 isted radionuclide production unsuitable at present for clinical applicati
 ons\, though in some cases HI cross sections are comparable with -parti
 cle activation cross sections. The high current ECR ion sources may addres
 s this limitation in future. Nevertheless\, the neutron deficient radionuc
 lides are comparatively short-lived and therefore highly suitable for trac
 er studies including biological systems. \nIn the conference\, I shall bri
 efly discuss the recent results obtained by our group on heavy ion assiste
 d production of radionuclides. This includes production of 149Tb\, 149Gd\,
  73As\, 75Se\, 209-211At\, 97Ru\, etc. In many cases\, we have measured cr
 oss section for production of these radionuclides and compared with the th
 eoretical prediction. The efficient and simple separation chemistry has be
 en developed in each case. Apart from conventional liquid liquid extractio
 n techniques\, we have also used aqueous biphasic extraction system (ABS)\
 , taking polyethylene glycol (PEG-4000) and solution of various salts for 
 separation of no-carrier-added radionuclide from the target matrix. Due to
  the absence of organic solvents\, ABS can be viewed as greener technique.
 \n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=243&sessionId=2
 3&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=243&sessionId=2
 3&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Recent advances in large scale isotope productio
 n at LANL
DTSTART;VALUE=DATE-TIME:20120919T100000Z
DTEND;VALUE=DATE-TIME:20120919T102000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-242@cern.ch
DESCRIPTION:Speakers: Dr. NORTIER\, Francois (Los Alamos National Laborato
 ry\, USA)\nLarge scale production of isotopes proceeds at the Isotope Prod
 uction Facility (IPF) of the Los Alamos National Laboratory (LANL)\, using
  intense 100 MeV proton beams.  The main metric of this program’s succes
 s is the reliable time-critical delivery of large quantities of high-purit
 y medical isotopes\, which in turn depends upon many aspects including rob
 ust high power targetry\, availability of intense proton beams and the abi
 lity to modify the primary beam energy.  The talk will highlight recent ad
 vances at LANL on these fronts\, which will further elevate the institutio
 n’s stature as a world leader in providing both large and small quantiti
 es of a wide variety of radioisotopes to users.\nSuccessful efforts of the
  LANSCE accelerator team in improving the 201 MHz Drift Tube LINAC operati
 ons\, resulted in recent demonstrations of a 40 MeV\, 250 µA capability a
 nd of 100 MeV\, 360 µA high  current operation of the LINAC.  These advan
 ces combined with the developing worldwide short supply of isotopes like S
 r-82 and Ge-68 as well as the emerging demand for therapy isotopes such as
  Ac-225 intensified the LANL efforts to advance understanding of and contr
 ol over failure mechanisms occurring in high power production targets.  Ad
 vances include the development of a next generation of RbCl salt targets a
 nd Rb-metal targets for increased Sr-82 production\, research focused on u
 nderstanding of failure mechanisms of Nb encapsulated Ga targets used in t
 he large scale production of Ge-68\, and the development of a first genera
 tion high current Th metal target design  for Ac-225 production.  \nAnothe
 r exciting new development includes efforts focused on the parasitic utili
 zation of secondary neutrons for smaller scale isotope production that wil
 l significantly expand the IPF production capability with no negative impa
 ct on the oversubscribed proton beam time.\n\nhttp://indico.cern.ch/contri
 butionDisplay.py?contribId=242&sessionId=24&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=242&sessionId=2
 4&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Archaeometry with INAA at the Research Reactor TRIGA Mainz
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-102@cern.ch
DESCRIPTION:Speakers: Mr. STIEGHORST\, Christian (Institut für Kernchemie
 \, Johannes Gutenberg-Universität Mainz\, Germany)\nAt the research react
 or TRIGA Mark II of the Institute for Nuclear Chemistry of the Johannes Gu
 tenberg-Universität Mainz\, Germany\, the interdisciplinary field of arch
 aeometry is studied by instrumental neutron activation analysis (INAA). Cu
 rrently the work is concentrated on three different projects in archaeolog
 ical context: Provenance analyses of ancient Roman limestone findings in t
 he Rhine-Moselle region\, determination of the composition of glass beads 
 of the late La Tène era\, which were excavated in southern Bavaria\, and 
 the analysis of sinter profile from ancient Mediterranean aqueducts to int
 erpret its layers as climate archives. For all samplings\, a method with a
  low risk of contamination is applied. To get a wide spectrum of elements 
 (chemical fingerprint)\, the irradiations and the gamma-ray measurements a
 re adjusted to the sample composition.\n\nFor the provenance project ancie
 nt limestone quarries as well as interesting archaeological objects are pr
 ospected and systematically sampled. Chemical fingerprints measured by INA
 A combined with multivariate statistics are used to determine the origin o
 f the objects to shed light on the complexity of logistics\, transport and
  trade routes in former times. \n\nGlass beads from an ancient ritual plac
 e near Oberammergau in Bavaria\, Germany are analyzed via INAA to determin
 e the glass type\, coloring elements and trace elements. The lanthanide co
 ncentrations deliver information about the raw glass production and give a
 rchaeologists clues as to the origin of the raw materials. Measurements fr
 om X-ray photoelectron spectroscopy together with the results of the INAA 
 analyses provide insight into the historic manufacturing process of the be
 ads.\n\nTo garner a better understanding of extreme weather event risks an
 d the frequency of earthquakes in the present\, the knowledge of the occur
 rence of these events for long periods of time is necessary. In the initia
 ted project\, sinter layers from ancient aqueducts are used as climate arc
 hives with proper chronological resolution.\n\nhttp://indico.cern.ch/contr
 ibutionDisplay.py?contribId=102&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=102&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Characterization of the Natural Organic Matter (NOM) by ultrafiltr
 ation and fluorescence in a groundwater plume contaminated with 60Co and 1
 37Cs
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-103@cern.ch
DESCRIPTION:Speakers: Dr. CARON\, François (Chemistry and Biochemistry De
 partment\, Laurentian University\, Canada)\nNatural Organic Matter (NOM) i
 s a collection of molecules originating from the decomposition of built bi
 omass\, and also from exudates from biological activities.  The constituen
 ts of NOM are poorly characterized molecules of various molecular sizes an
 d functional groups that could affect the fate of radionuclides and other 
 contaminants.  In this work\, groundwaters have been sampled near a contam
 inated area in the Canadian boreal shield and size-fractionated by ultrafi
 ltration (5000 Da cut-off) to determine the associations of selected radio
 nuclides (60Co\, 137Cs) with colloidal-sized fractions of NOM.  Solid phas
 e extraction (SPE) was also used in tandem with fluorescence analysis of t
 he fractions\, to elucidate the changes in the chemical nature of the NOM.
   Fluorescence is a powerful tool that can track the optical characteristi
 cs of the NOM constituents in an Excitation-Emission Matrix (EEM).  The EE
 M\, in turn\, is numerically decomposed into individual and independent co
 mponents\, defined as humic-like\, fulvic-like\, and protein-like.  \n\nOu
 r results have revealed consistent trends over the years (2004-2010): an u
 ncontaminated station had a small colloidal NOM content (typically 95% of 
 the total)\, whereas 60Co was mostly in the filtered fraction (70-90%).  W
 hen the samples were submitted to SPE and fluorescence\, a systematic remo
 val of the protein-like NOM was found\, without affecting the humic- and f
 ulvic-like components.  Cobalt-60 and 137Cs were affected only to a small 
 extent\, suggesting that these were associated with the humic- and fulvic-
 like NOM\, and not the protein-like NOM.  This finding is intriguing and u
 nique\, as the protein-like NOM was found only in the contaminated sites. 
  Applications of fluorescence\, as a new tool to this sampling\, will be d
 iscussed further.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribI
 d=103&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=103&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Production and purification of 56Co at the Leipzig cyclotron
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-100@cern.ch
DESCRIPTION:Speakers: Dr. MANSEL\, Alexander (HZDR - Research Site Leipzig
 \, Germany)\, Dr. FRANKE\, Karsten (HZDR - Research Site Leipzig\, Germany
 )\n60Co (T1/2 = 5.27 a) is one of the most used radionuclide for steriliza
 tion of medical equipment\, as a radiation source for medical radiotherapy
 \, industrial radiography and food irradiation due to the high gamma-energ
 y of 1.33 MeV. In case of release in the geosphere\, e.g. soil and aquatic
  systems\, the migration behaviour of cobalt is not well understood. For g
 eochemical investigations\, e.g. migration and adsorption studies in soil 
 and rock formations\, the short-lived isotope 56Co (T1/2 = 77 d) can be us
 ed.\nWe produced 56Co at a recently installed 18 MeV-cyclotron by using th
 e nuclear reaction 56Fe(p\,n)56Co.[1] The target was prepared by pressing 
 metallic iron powder into an aluminium plate and cover it with an aluminiu
 m foil. After the irradiation with 11 MeV protons for 1 h at a current of 
 25 µA\, the iron was dissolved with a mixture of concentrated HCl and con
 centrated H2O2.[2] The separation of 56Co from the target material was don
 e by liquid-liquid extraction with methyl-tert-butylether (MTBE) from 5.2 
 M HCl.[3] Alternatively\, an anionic exchange with DOWEX 1x8 as a column m
 aterial can be used.[4] Due to the shorter separation time the liquid-liqu
 id extraction is preferred. The radiochemical yield was 82% ± 6%. The act
 ivity concentration in the 56Co stock solution was ~4.5 MBq / ml.\n\n[1] J
 enkins\, I. L.\, Wain\, A. G.\, (1970) J. Inorg. Nucl. Chem. 32(5) 1419-14
 25.\n[2] Lagunas-Solar\, M. C.\, Jungerman\, J. A.\, (1979) Int. J. Appl. 
 Radiat. Isot. 30(1) 25-32.\n[3] V. Wiskamp\, S. Zenker\, (1997)\, Eisenext
 raktion mit tertiärem Butylmethylether. CLB 48 (Beilage Memory) 22.\n[4] 
 Kraus\, K. A.\, Moore\, G. E.\, (1953) J. Am. Chem. Soc. 75(6) 1460-1462.\
 n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=100&sessionId=26
 &confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=100&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Characterization of silicon for photovoltaic applications with INA
 A and PGAA
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-101@cern.ch
DESCRIPTION:Speakers: Dr. WIEHL\, Norbert (University Mainz\, Germany)\nTh
 e required impurity level for silicon used in solar cell production can be
  much higher compared to the demand in the electronic industry [1]. Theref
 ore processes are investigated to clean the raw silicon to an impurity lev
 el necessary for photovoltaic applications. Of special interest is the imp
 urity level of the 3d transition metals and of the dopant element boron. T
 ransition metals of the 3d – series form deep levels in the energy gap o
 f silicon and act as recombination centres for the charge carriers thus de
 grading the efficiency of solar cells.\nA major part of the purification o
 f silicon takes place during directional crystallization because most impu
 rities have a segregation coefficient k \n\nhttp://indico.cern.ch/contribu
 tionDisplay.py?contribId=101&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=101&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Separation of no-carrier-added 109Cd from natural silver target us
 ing RTIL 1-butyl-3-methylimidazolium hexafluorophosphate
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-249@cern.ch
DESCRIPTION:Speakers: Prof. LAHIRI\, Susanta (Saha Institute of Nuclear Ph
 ysics\, 1/AF\, Bidhannagar\, Kolkata-700064\, India)\nThe room temperature
  ionic liquid (RTIL)\, 1-butyl-3-methylimidazolium hexafluorophosphate [C4
 mim][PF6]  has found application in separation of a range of metal ions re
 placing volatile and toxic traditional organic solvents in liquid-liquid e
 xtraction (LLX) systems. Despite of disadvantage of probable release of HF
  in acidic reaction\, the RTIL [C4mim][PF6] is used widely in developing g
 reen processes in analytical chemistry as it is hydrophobic in nature\, la
 cks vapor pressure\, and can be synthesized easily. Favorable half-life of
  109Cd (461.4 d) allows its use in the field of medical science\, environm
 ental science as well as in technology. Several reports are also available
  on the production and separation of no-carrier-added (NCA) 109Cd. This pa
 per reports the separation of NCA 109Cd from the natAg target using [C4mim
 ][PF6] in LLX. The 109Cd was produced by bombarding a natAg foil (25.4 mg/
 cm2 thick) by 30 MeV α-particles at the Variable Energy Cyclotron Centre\
 , Kolkata\, India. After the decay of all short-lived products\, NCA 109Cd
  was separated from the bulk Ag using [C4mim][PF6] as extractant in combin
 ation with HNO3 where ammonium pyrrolidine dithiocarbamate (APDC) was used
  as a complexing agent. At the optimum condition\, 3 M HNO3\, 0.2 mL 0.1 M
  APDC and 1.25 mL [C4mim][PF6]\, bulk Ag was extracted to the IL phase bin
 ding with APDC\, leaving ~ 85% NCA 109Cd in the aqueous phase. The ionic l
 iquid was also recovered by washing the IL phase with 5 M HNO3. The report
 ed separation technique is simple\, fast and in concurrence with green che
 mistry approach.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId
 =249&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=249&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Nuclear and radiochemistry education in European
  Universities
DTSTART;VALUE=DATE-TIME:20120920T122000Z
DTEND;VALUE=DATE-TIME:20120920T124000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-248@cern.ch
DESCRIPTION:Speakers: Prof. LEHTO\, Jukka (Laboratory of Radiochemistry\, 
 University of Helsinki\, Finland)\nWithin the EU project CINCH (Cooperatio
 n in education in nuclear chemistry) a survey on education of nuclear and 
 radiochemistry (NRC) in European universities was produced by the Universi
 ty of Helsinki\, Laboratory of Radiochemistry. Altogether 22 countries and
  69 universities were covered by internet survey and by sending a question
 naire to appropriate departments. 42 universities\, including most relevan
 t institutions\, replied to the questionnaire. The survey was mainly focus
 ed on teaching at the master’s level which is the typical level of teach
 ing. 83% of the universities give NRC teaching at the MSc level or both at
  MSc and BSc levels and 17% only at the BSc level. In addition\, a number 
 of universities have high quality doctoral programmes in NRC but have no o
 r only limited teaching at lower levels. In general\, the teaching program
 mes at various universities are very diverse.\n\nOnly a limited number of 
 universities have specific MSc and BSc programmes for NRC. Only two univer
 sities (3% of surveyed universities) have a BSc programme and five univers
 ities (7%) an MSc programme. In addition to these\, specialization in NRC 
 within chemistry MSc programmes is possible in 25 universities (36%). Howe
 ver\, in most of the universities (57%) only a few courses in NRC are taug
 ht under various MSc programmes. In the NRC master’s programmes and in s
 pecializations (44 altogether) most (55%) universities focus on basic NRC 
 while 20% of them focus in environmental radioactivity/radioecology\, 16% 
 in nuclear energy and materials and 9% in radiopharmaceutical chemistry.\n
 \nMost of the courses given (57%) can be categorized to basic NRC which ma
 inly covers basic nuclear physics as well as detection and measurement of 
 radiation. In addition\, 14% of the courses deal with environmental radioa
 ctivity and radioecology\, 11% analytical radiochemistry\, 7% nuclear ener
 gy and materials 7% radiopharmaceutical chemistry. \n\nBoth the survey rep
 ort and the list of universities giving NRC education have been published 
 at the CINCH home page http://cinch-project.eu/.\n\nhttp://indico.cern.ch/
 contributionDisplay.py?contribId=248&sessionId=29&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=248&sessionId=2
 9&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Radiochemical separation of uranium and protactinium from neutron 
 irradiated thorium.
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-104@cern.ch
DESCRIPTION:Speakers: Dr. CHAJDUK\, Ewelina (Institute of Nuclear Chemistr
 y and Technology\, Dorodna 16\, 03-195 Warsaw\, Poland)\nThe aim of this w
 ork was elaboration of radiochemical scheme for separation micro-amounts o
 f uranium and protactinium from macro-amounts of Th\, what can be helpful 
 in nuclear power engineering for the analysing thorium-uranium fuel cycle 
 as well as IV generation nuclear reactors.  Naturally abundant isotope of 
 thorium\, 232Th is the fertile material. In the nuclear reactor\, 232Th is
  transmuted into the fissile artificial uranium isotope 233U.. Elaborated 
 separation procedure is based on extraction chromatography\, which combine
 s the selectivity of liquid-liquid extraction with the rapidity and quanti
 tativity of chromatographic methods. In first step\, Pa is quantitatively 
 isolated from micro-amount of U and macro-amount of 232Th on the column fi
 lled with TOPO supported on hydrophobic sorbent. Next\, effluent  containi
 ng thorium and U traces is loaded onto the column filled with quaternary a
 liphatic amine and an elution is conducted with a mixture of nitric and hy
 drofluoric acids with an addition of aluminium nitrate and H2O. Uranium is
  selectively eluted with first 5-10 mL\, whereas Th is eluted in next  35-
 40 mL.\n\n\n\nThis work was partly supported by the POIG grant No: POIG .0
 1.03.01-00-076/08\n\nhttp://indico.cern.ch/contributionDisplay.py?contribI
 d=104&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=104&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Radiochemical separation of arsenic from selenium and its potentia
 l usage in generator isotope production.
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-105@cern.ch
DESCRIPTION:Speakers: Dr. CHAJDUK\, Ewelina (Institute of Nuclear Chemistr
 y and Technology\, Dorodna 16\, 03-195 Warsaw\, Poland)\nThe potential usa
 ge of  arsenic isotopes for nuclear medicine has been reported recently. O
 ne of the way for obtaining  appropriate radioarsenic species  is using ra
 dionuclide generator\, where As  is formed by the radioactive decay\, eg. 
 72Se  72As. A new radiochemical separation scheme based on extraction c
 hromatography for isolation As from Se is presented. The distribution coef
 ficients of  As and Se on  prepared sorbents (selected aromatic o-diamines
  supported on polystyrene adsorbents) were determined in order to find the
  best condition for separation of both elements. Batch experiments were ve
 rified by column studies.  Elaborated radiochemical separation scheme insu
 res high selectivity and radionuclide purity of separated arsenic fraction
 \, whereas examined sorbents have been found to have a very high selectivi
 ty with reference to selenium (IV). Arsenic is easily eluted by diluted HC
 l and NaCl solutions. The present separation scheme based on extraction ch
 romatography\, which could be used to designing a new 72Se/72As generator.
   \n\nAcknowledgments: This work was partly supported by the grant of Poli
 sh Ministry of Science and Higher Education\, Poland\, (Nr 2713/B/H03/2011
 /40)\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=105&session
 Id=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=105&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:64Cu and 67Cu Production and Purification Research at the Radiatio
 n Science and Engineering Center at the Pennsylvania State University
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-39@cern.ch
DESCRIPTION:Speakers: Prof. UNLU\, Kenan (The Pennsylvania State Universit
 y\, USA)\nThe United States faces a shortage of medical isotopes for clini
 cal use and for research and development of new therapeutic and diagnostic
  procedures.  The Society of Nuclear Medicine and the National Cancer Inst
 itute in the USA have noted that 64Cu and 67Cu isotopes are in short suppl
 y.  The isotope 67Cu (t1/2 = 61.83 h) emits a beta particle useful for can
 cer treatment and has several gamma-ray emissions appropriate for medical 
 imaging.  As a positron-emitter (17.9%) and a β--emitter (39.0%)\, 64Cu (
 t1/2 = 12.7 h) is used for positron emission tomography scans and to study
  copper behavior in the body for the diagnosis of metabolic diseases.  The
  small amounts of 64Cu and 67Cu currently available are produced via charg
 ed particle reactions\, but existing accelerators are in high demand for o
 ther applications.  To expand the production capabilities for these two is
 otopes\, the Radiation Science and Engineering Center at the Pennsylvania 
 State University is investigating reactor-based production methods via the
  (n\,p) reactions  and  .  These reactions require neutrons with energies 
 above 1 MeV\, which are available in the central thimble of the Penn State
  Breazeale Nuclear Reactor at a flux of 1.6x1013 n/cm2/s.  To reduce the p
 roduction of unwanted radioisotopes\, 99% isotopically enriched 64Zn and 9
 4% enriched 67Zn are used.  64Zn and 68Zn can activate in measureable quan
 tities to radioactive 65Zn (t1/2 = 243.8d) and 69Zn (t1/2 = 13.76 h) due t
 o thermal neutrons\; both types of targets can be shielded to reduce these
  activation products.  Post-irradiation\, quartz-encapsulated zinc oxide t
 argets are dissolved in acid\, followed by purification via one or more io
 n exchange methods.  Although the cross-sections for these (n\,p) reaction
 s are low\, our development of a reactor-based transmutation production me
 thod for 64Cu and 67Cu offers several advantages:  large amounts of sample
  may be irradiated simultaneously and the product is carrier-free\, making
  it highly isotopically and chemically pure. Experimental details and some
  results for this reactor-based alternative 64Cu and 67Cu production and p
 urification method will be presented.\n\nhttp://indico.cern.ch/contributio
 nDisplay.py?contribId=39&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=39&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Curriculum Development for Nuclear Fuel Chemis
 try\, Reprocessing and Separation Chemistry\, and Radioactive Waste Manage
 ment at the Pennsylvania State University
DTSTART;VALUE=DATE-TIME:20120920T132000Z
DTEND;VALUE=DATE-TIME:20120920T133500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-38@cern.ch
DESCRIPTION:Speakers: Prof. UNLU\, Kenan (The Pennsylvania State Universit
 y\, USA)\nRecent curriculum development in the Department of Mechanical an
 d Nuclear Engineering at Penn State University includes Laboratory Experim
 ents in Applied Nuclear and Radiochemistry and a new Nuclear Security Educ
 ation Program (NSEP) being develop in collaboration with MIT and TAMU with
  the support of the DOE-NNSA\, Global Threat Reduction Initiatives. To sup
 plement the NSEP and attract more undergraduate students in radiochemistry
 \, development of several new course modules has been started at Penn Stat
 e with US Nuclear Regulatory Commission funding.  The course modules are s
 tructured in two tiers\, introductory and advanced\; students will be requ
 ired to satisfactorily complete the two introductory modules before enroll
 ing in the advanced modules. The introductory module Introduction to Actin
 ide and Lanthanide Chemistry provides a review of basic nuclear and chemic
 al concepts\, as well as more advanced concepts on the electronic structur
 e\, aqueous behavior\, and solid behavior of the actinide and lanthanide e
 lements.  Introduction to the Nuclear Fuel Cycle introduces the most commo
 n types of nuclear reactors and the collective process of the nuclear fuel
  cycle\, including fuel harvesting\, processing\, use\, and disposal.  Fou
 r advanced course modules provide in-depth instruction on specialized area
 s of the fuel cycle and actinide chemistry.   Nuclear Fuel Chemistry prese
 nts the chemistry of nuclear fuels in three parts: the characteristics and
  manufacture of nuclear fuel\; alteration processes in nuclear fuel during
  irradiation\; and post-irradiation chemical behaviors of nuclear fuel und
 er storage or disposal conditions.  Nuclear Fuel Reprocessing and Separati
 ons Chemistry reviews the radionuclide inventories for used commercial fue
 l bundles of typical burnup levels\, as well as the overall objectives and
  outcomes required of any potential reprocessing method.  Detailed studies
  of the chemistry of several important historical and research-scale repro
 cessing methods are emphasized.  Radioactive Waste Management presents cur
 rent and potential waste disposal options for all parts of the nuclear fue
 l cycle.  In Environmental Radiochemistry\, students are presented with th
 e most important radionuclides of environmental concern and the environmen
 tal processes that influence their behavior. Details of the development of
  radiochemistry course modules at Penn State will be presented.\n\nhttp://
 indico.cern.ch/contributionDisplay.py?contribId=38&sessionId=29&confId=183
 405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=38&sessionId=29
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Cyclotron production of radionuclides with mediu
 m-energy proton beams and high-power targetry
DTSTART;VALUE=DATE-TIME:20120919T092000Z
DTEND;VALUE=DATE-TIME:20120919T094000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-32@cern.ch
DESCRIPTION:Speakers: Dr. STEYN\, G. (iThemba LABS\, South Africa)\nAt iTh
 emba LABS\, proton beams of 66 MeV are used for the routine production of 
 radionuclides and for neutron therapy. Between treatment irradiations\, th
 e beam is switched to the radionuclide production vaults and vice versa. D
 edicated beam time for radionuclide production is also scheduled at night.
  \n\nIn recent years\, several facility upgrades and new additions had bee
 n geared towards increasing the radionuclide production capacity by increa
 sing the beam intensity. The development of suitable targetry to exploit t
 he higher beam intensities were pursued in parallel. In addition\, a beam 
 splitter was developed and put into routine operation\, which makes it pos
 sible to bombard two radionuclide production targets simultaneously. These
  developments\, together with the addition of a new vertical beam target s
 tation (VBTS) led to a three-fold increase in production capability. \n\nT
 he main accelerator developments to achieve higher beam intensities were t
 he addition of flat-topping resonators to one of the solid-pole injector c
 yclotrons (SPC1) and the separated sector cyclotron (SSC) as well as an ad
 ditional RF buncher in the transfer beam line between them. This also requ
 ired improved beam diagnostics\, including non-destructive beam position m
 onitors for continuous display of the beam position as well as stray-beam 
 monitors installed at regular intervals along all the high-energy beam lin
 es leading to the radionuclide production vaults. Extraction of 66 MeV pro
 ton beams with intensities up to 300 micro-ampere is now routinely possibl
 e\, which can be accommodated on certain targets if rapid beam sweeping is
  employed.\n\nThe evolution of the radionuclide production programme at iT
 hemba LABS with emphasis on the developments over the last circa 5 years w
 ill be presented. This will include an account of our experiences with hig
 h-power targets\, in particular the VBTS tandem targets for the production
  of Na-22\, Ge-68 and Sr-82.\n\nhttp://indico.cern.ch/contributionDisplay.
 py?contribId=32&sessionId=24&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=32&sessionId=24
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Japanese Green Tea: radioactivity measurements\,
  radiochemical extraction yield determination and some radioprotection con
 siderations.
DTSTART;VALUE=DATE-TIME:20120921T094000Z
DTEND;VALUE=DATE-TIME:20120921T100000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-108@cern.ch
DESCRIPTION:Speakers: Dr. MANERA\, Sergio (LENA - University of Pavia\, It
 aly)\nThe aim of this study\, performed on a sample of 2011 (year of the n
 uclear accident of Fukushima) green tea from the Japanese Prefecture of Sh
 izuoka\, was to measure by gamma spectroscopy the natural and artificial r
 adioactivity and the dishomogeneity index of the sample\, but also a more 
 in depth investigation of the ratio of the two radionuclides of Cesium and
  the relative transfer mechanisms of radioactivity to humans under normal 
 conditions of use of the product. To do so we reproduced in laboratory the
  common domestic preparation of the tea beverage doing 4 different extract
 ions and determining the relative yields of extraction for radiocaesium an
 d natural Potassium from the leaves of tea into the beverage. As a consequ
 ence we present analytical data to better assess the total radioactivity e
 ffectively ingested by consumers of this product and add some consideratio
 ns on the food safety limits.\nThen we added some basic radioprotection co
 nsiderations to show some common misconceptions in the evaluation of the c
 ompliance of this kind of matrices to the food safety limits set by the Ja
 panese law in respect to the FAO’s “Codex Alimentarius” recommendati
 ons. Starting from the effectively ingested radioactivity we also show the
  rough committed relative dose for two categories of public: adult and inf
 ants. Seeing the good results of this work\, now our aim is to investigate
  further and more widely both the concentration of radioactive Cesium and 
 the extraction yields in japanese tea samples\, including other prefecture
 s of origin and possibly other types of tea. The goal is to confirm the va
 lues of the calculated extraction yields of this batch. It’s also import
 ant to assess the extraction yields starting from the first year after the
  one of the nuclear accident because the first year is still affected by b
 oth fallout and root uptake of Cesium in vegetables while starting from 20
 12 only the root uptake pathway will be important.\n\nhttp://indico.cern.c
 h/contributionDisplay.py?contribId=108&sessionId=31&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=108&sessionId=3
 1&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Exploration of the metallic character of astat
 ine
DTSTART;VALUE=DATE-TIME:20120918T085500Z
DTEND;VALUE=DATE-TIME:20120918T091000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-35@cern.ch
DESCRIPTION:Speakers: MONTAVON\, Gilles (Subatech\, France)\nAstatine 211 
 is considered to be one of the most promising candidates for targeted alph
 a therapy (TAT)1\, 2 and it is the subject of a wide research program in N
 antes (France).\nVery few data on the chemistry of astatine (At) are avail
 able. On the one hand\, At is a rare element and it has only short half-li
 fe radioactive isotopes. On the other hand\, it is an “invisible” elem
 ent: the amount of At-211 produced allows working at ultra trace concentra
 tions (typically 10-11 to 10-15 M) and no spectroscopic techniques can be 
 used to estimate At characteristics at the molecular level. As a result\, 
 At chemistry is not well understood. \nBased on these considerations\, a r
 esearch program has started in Nantes to explore the fundamental propertie
 s of At using a multi-disciplinary approach combining radiochemistry\, ana
 lytical chemistry and molecular modelling competences. The object of this 
 contribution is to present the main advances obtained during the last 8 ye
 ars as regards especially to the particular metallic character of astatine
 . The methodology enabled us to define a Pourbaix diagram (Eh/pH diagram) 
 for At in non-complexing acidic aqueous medium. We showed the existence of
  At-\, and two stable At+ and AtO+ metallic forms of astatine.3\, 4 This h
 ighlighted the metallic character of At by comparison with others halogens
 \, as it was already proposed in the 60’s.5 Our recent results on the ch
 emical reactivity of AtO+ demonstrate the potentiality to form both coordi
 nation and covalent bondswith organic and inorganic ligands.6\, 7\n\n\n1.	
 D. S. Wilbur\, Current Radiopharmaceuticals\, 2008\, 3\, 144-176.\n2.	M. R
 . Z. Vaidyanathan G.\, Current Radiopharmaceuticals\, 2008\, 1\, 177-196.\
 n3.	J. Champion\, C. Alliot\, E. Renault\, B. M. Mokili\, M. Cherel\, N. G
 alland and G. Montavon\, The Journal of Physical Chemistry A\, 2010\, 114\
 , 576-582.\n4.	A. Sabatié-Gogova\, F. Pottier\, J. Champion\, S. Huclier\
 , N. Michel\, N. Galland\, Z. Asfari\, M. Chérel and M. G.\, Analytical C
 himica acta\, 2012\, 721\, 182.\n5.	E. H. Appelman\, J. Am. Chem. Soc.\, 1
 961\, 83\, 805-807.\n6.	J. Champion\, C. Alliot\, S. Huclier\, D. Deniaud\
 , Z. Asfari and G. Montavon\, Inorganica Chimica Acta\, 2009\, 362\, 2654-
 2661.\n7.	J. Champion\, M. Seydou\, A. Sabatie-Gogova\, E. Renault\, G. Mo
 ntavon and N. Galland\, Physical Chemistry Chemical Physics\, 13\, 14984-1
 4992.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=35&session
 Id=20&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=35&sessionId=20
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Plutonium radionuclides in stratospheric and t
 ropospheric air: new evidences from measurements in high altitude aerosols
DTSTART;VALUE=DATE-TIME:20120921T111000Z
DTEND;VALUE=DATE-TIME:20120921T112500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-34@cern.ch
DESCRIPTION:Speakers: Dr. CORCHO ALVARADO\, José Antonio (Institute of Ra
 diation Physics\, Lausanne University Hospital\, Switzerland)\nHere we rep
 ort some new experimental results on the content of the long-lived plutoni
 um radionuclides (238Pu\, 239\,240Pu\, 241Pu) in the upper tropospheric an
 d lower stratospheric aerosols. Plutonium radionuclides have been injected
  into the atmosphere by different processes (ex. nuclear weapon tests (NWT
 )\, burn-up of the satellite SNAP-9A\, accidents in nuclear facilities\, e
 tc.). However\, stratospheric component stems mainly from high yield (Mega
 ton) atmospheric nuclear explosions and represents the principal source of
  global contamination with plutonium (Pu). The aerosol samples were collec
 ted periodically since 1970 in the frame of the environmental surveillance
  programme of Switzerland. Air volumes up to a few thousands cubic meters 
 were filtered through cellulose filters during stratospheric flights using
  military airplanes. \nOur measurements show that Pu radionuclides are pre
 sent in the stratosphere at higher levels than in the troposphere. The iso
 tope ratios indicate that the main origins of Pu in the stratosphere are t
 he NWTs and the burn-up of the satellite SNAP-9A. The lower content in the
  troposphere reveals that dry and wet deposition removes efficiently most 
 of the Pu within a few weeks to months. This is not the case for the strat
 osphere where plutonium has a much longer residence time because of its th
 ermal stratification that separates it from the troposphere. Nevertheless\
 , the analysis of aerosols collected during the passage of the Eyjafjallaj
 ökull volcano ash plume in 2010 revealed high levels of Pu in the troposp
 here\, comparable to the values typically observed in the stratosphere. Th
 e explosive eruption of this volcano threw volcanic fine grained ash into 
 the stratosphere that quickly mixed with stratospheric aerosols and then m
 ay have transported some stratospheric Pu into the troposphere.\n\nhttp://
 indico.cern.ch/contributionDisplay.py?contribId=34&sessionId=31&confId=183
 405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=34&sessionId=31
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Attachment of APTES ((3-aminopropyl)triethoxysilane) to silica for
  sorption and selective removal of radionickel from solution
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-109@cern.ch
DESCRIPTION:Speakers: Mr. HOLT\, James (Loughborough University\, UK)\nThe
  main aim of this research is to design and develop a novel class of selec
 tive sorbents or sequestrating agents for various actinides\, fission prod
 ucts\, heavy metals and groundwater contaminants using a bespoke modular d
 esign of solid-supported polymers and containment-specific ligand groups.\
 nOur current research has seen us attach the ligand known as APTES straigh
 t to the surface of silica gel (mean particle size\; ca. 70 μm) and high 
 surface area fumed silica (mean particle size\; ca. 0.007 μm).  \nBy util
 ising two different silica types\, the authors have been able to investiga
 te the efficiency of ligand attachment to different types of silica.  Foll
 owing successful sequestration of inactive transition metals including cob
 alt\, nickel\, copper and zinc\, we have extended our research by using th
 e radioactive isotope of nickel-63.  \nUsing a range of concentrations fro
 m 2.5 ppm to 80 ppm\, the silica attached APTES has successfully sequestra
 ted Ni-63.  To make the investigation more realistic and be able to relate
  it to a real case scenario\, competitive ions (in this case sodium and ca
 lcium) were added to further the study.  It has been shown that the nickel
  sequestration is not as affected by the addition of these ions as one mig
 ht expect. Sequestration is still observed at a similar level to deionised
  water.  \nRd’s for the sequestration of Ni-63 from deionised water rang
 e from 4 x 104 ml/g to 1.2 x 107 ml/g compared to 5.3 x 104 ml/g to 7.9 x 
 105 ml/g for competitive calcium in solution and 1.2 x 105 ml/g to 7.3 x 1
 06 ml/g for competitive sodium sequestration.  Isotherms have also been pr
 oduced across a pH range from 5.01 to 6.80 before addition of the material
 \, to a final pH of 6.90 to 9.49 depending on the original concentration a
 nd competitive ions in solution.\n\nhttp://indico.cern.ch/contributionDisp
 lay.py?contribId=109&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=109&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Synthesis and Characterization of Radiolabelled Silver Nanoparticl
 es
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-162@cern.ch
DESCRIPTION:Speakers: Dr. ICHEDEF\, Cigdem (Joint Research Centre\, Instit
 ute for Health and Consumer Protection\; Ege University Institute of Nucle
 ar Sciences\, Turkey)\nSilver nanoparticles (AgNPs) have a wide range of a
 pplications in cosmetics\, wound dressings\, food packaging and also in me
 dical sciences such as drug and gene delivery systems because of their eff
 ective antibacterial properties [1\,2]. This wide usage increases environm
 ental and human exposure to AgNPs which may cause undesirable biological a
 nd ecological effects. Recent studies showed that AgNPs have significant t
 oxic effects on cells and the particle properties such as size\, surface a
 rea\, solubility etc. may alter the toxicity of the particles [2-4]. There
 fore it is essential to investigate their behaviour in complex matrices. T
 he chemical behaviour of silver and silver ions is in biological and envir
 onmental media is extremely complex due to \na)relative easy which silver 
 may be oxidised or reduced\nb)photochemical activity of both the metal and
  its salts\nc)the large number of low solubility complexes or compound whi
 ch may form with silver  ions.\nAll of these factors can create many diffi
 culties and uncertainties when attempting to achieve accurate and reproduc
 ible analysis of low levels of silver by conventional trace analysis metho
 ds such as ICP-MS. Many of these problems can be reduced or eliminated if 
 silver detection\, tracing and quantification can be done using radiotrace
 rs. Use of radioactive NPs as tracers has several advantages with respect 
 to the high sensitivity and accuracy of radiolabelling techniques [5].\nIn
  this study radiolabelled AgNPs were synthesized by reduction of silver ni
 trate with sodium borohydride. The 105Ag and 110mAg were prepared by proto
 n and deuteron irradiation of silver foils respectively at the JRC Scandit
 ronix MC 40 Cyclotron\, followed by dissolution in nitric acid and evapora
 tion to dryness. Due to a higher production yield\, 105Ag was used for rad
 iolabeling studies. The characterization of the nanoparticles was performe
 d using DLS\, zeta potential and XRD analysis. The size distribution of th
 e 105AgNPs was found to be centred around 20 nm according to the DLS measu
 rements and were colloidally stable for at least 21 days. It was observed 
 that size distribution and surface charge of the radiolabeled nanoparticle
 s was very similar to those obtained by synthesis using a non-radioactive 
 source of silver.  Silver ion leaching and particles stability in differen
 t media were assessed.\nReferences\n\n[1]	Zhang W.\, Yao Y.\, Li K.\, Huan
 g Y.\, Chen Y.\, Influence of dissolved oxygen on aggregation kinetics of 
 citrate-coated silver nanoparticles. Environmental Pollution\, 159 (2011) 
 3757-3762.\n[2]	Kim T.H.\, Kim M.\, Park H.S.\, S.S. Ueon\, Gong M.S.\, Ki
 m H.W.\, Size-dependent cellular toxicity of silver nanoparticles. 2012\, 
 DOI: 10.1002/jbm.a.34053.\n[3]	Römer I.\, White T.A.\, Baalousha M.\, Chi
 pman K.\, Viant M.R.\, Leada J.R.\, Aggregation and dispersion of silver n
 anoparticles in exposure media for aquatic toxicity tests. Journal of Chro
 matography A\, 1218 (2011) 4226– 4233.\n[4]	Samberg M.E.\, Oldenburg S.J
 .\, Monteiro-Riviere N.A.\, Evaluation of Silver Nanoparticle Toxicity in 
 Skin in Vivo and Keratinocytes in Vitro Environmental Health Perspectives.
  118 (2010) 407-413.\n[5]	Gibson N\, Holzwarth U\, Abbas K\, Simonelli F\,
  Kozempel J\, Cydzik I\, Cotogno G\, Bulgheroni A\, Gilliland D\, Franchin
 i F\, Marmorato P\, Stamm H\, Kreyling W\, Wenk A\, Semmler-Behnke M\, Buo
 no S\, Maciocco L\, Burgio N.\, Radiolabelling of engineered nanoparticles
  for in vitro and in vivo tracing applications using cyclotron accelerator
 s. Archives of Toxicology 85 (2011) 751-773.\n\nhttp://indico.cern.ch/cont
 ributionDisplay.py?contribId=162&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=162&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Decay data measurements on <sup>213</sup>Bi us
 ing recoil atoms
DTSTART;VALUE=DATE-TIME:20120917T141000Z
DTEND;VALUE=DATE-TIME:20120917T142500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-160@cern.ch
DESCRIPTION:Speakers: Dr. POMMÉ\, Stefaan (EC-JRC-IRMM\, Belgium)\n213Bi 
 is one of the most important &alpha-emitting nuclides used in targeted alp
 ha therapy (TAT) against cancer. It is readily available from the subseque
 nt &alpha-decay of 225Ac → 221Fr → 217At → 213Bi. The parent half-li
 fe is T1/2(225Ac)=9.920 (3) d (Pommé et al.\, in press)\, while 221Fr and
  217At are shorter-lived. 213Bi has a half-life of about 45.6 min and deca
 ys to the longest-lived alpha emitter 209Bi through two branches\, each in
 volving one &alpha-decay and two &beta-decays. An IAEA Coordinated Researc
 h Project has identified the need for a new half-life measurement of 213Bi
 .\nIn this work\, 213Bi has been separated from an open 225Ac source by co
 llecting recoil atoms onto a glass plate in vacuum. The activity of such r
 ecoil sources has been followed as a function of time\, using an ion-impla
 nted planar Si detector in quasi-2&pigreco geometry\, resulting in a new h
 alf-life value. Additional high-resolution alpha-spectrometry measurements
  were performed at a solid angle of 0.4% of 4π sr\, to verify the energie
 s and emission probabilities of the &alpha-emissions from the decay produc
 ts of 225Ac. For both experiments\, a description of the measurement metho
 d and data analysis is provided. The resulting decay data are given with a
 n uncertainty budget and compared with literature values.\n\nhttp://indico
 .cern.ch/contributionDisplay.py?contribId=160&sessionId=17&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=160&sessionId=1
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Spectroscopic Studies of Complexation Behaviour of Uranium(VI) by 
 Schiff Bases
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-176@cern.ch
DESCRIPTION:Speakers: Ms. LINDNER\, Katja (Helmholtz-Zentrum Dresden-Rosse
 ndorf\, Germany)\nUranium can be released into the natural environment esp
 ecially from mining areas by weathering\, erosion and anthropogenic activi
 ties as well as by nuclear incidents and thus represents a hazard potentia
 l for humans. New supramolecular complexing agents with N\, O\, S donor fu
 nction are developed for the use in nuclear field and environmental protec
 tion to separate the metals of the d- and f-block and thus to clean contam
 inated areas. An essential basic component of these new organic ligands ar
 e Schiff bases.\nIn this study the complexation of uranium(VI) with Schiff
  bases N-benzylideneaniline (NBA)\, 2-(2-hydroxybenzylidenamino)phenol (HB
 AP) and alpha-(4-hydroxyphenylimino)-p-cresol (HPIC) was investigated in a
 lcoholic solution using the UV-vis spectroscopy and time-resolved laser fl
 uorescence spectroscopy with ultrashort laser pulses (fs-TRLFS). Through t
 he change of the absorption or emission properties of organic ligands can 
 be observed the complexation with uranium(VI) and calculated corresponding
  complex formation constants.\nThe complexation of uranium(VI) with NBA wa
 s observed by a hypsochromic shift in the NBA band to 237 nm with the UV-v
 is spectroscopy. Investigations with the ligand HBAP show a bathochromic s
 hift to 281 nm. The UV-vis absorption spectra of HPIC with uranium(VI) sho
 w no spectral shift\, but a decrease in intensity of the double band at 28
 3nm and 332 nm in comparison to the free ligand. All three ligands form co
 mplexes MLx with more ligand molecules (x=2\,3).\nThe fs-TRLFS as a sensit
 ive speciation technique was used to determine the luminescence properties
  of formed complexes in the uranium(VI)-NBA\, uranium(VI)-HBAP and uranium
 (VI)-HPIC systems. The emission signals had a hypsochromic\, bathochromic 
 and hypsochromic shift in comparison to the emission maxima of the uncompl
 exed ligand. This fs-TRLFS investigation opens up the possibilities for th
 e determination of very short-lived complex species via the fluorescence o
 f the organic compounds by delocalized -electron systems.\n\nhttp://ind
 ico.cern.ch/contributionDisplay.py?contribId=176&sessionId=26&confId=18340
 5
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=176&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - The Behavior of Actinide Elements in Contaminate
 d Environments
DTSTART;VALUE=DATE-TIME:20120921T060000Z
DTEND;VALUE=DATE-TIME:20120921T062000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-60@cern.ch
DESCRIPTION:Speakers: Prof. CLARK\, Sue (Washington State University\, USA
 )\nSavannah River Site (SRS) is one of several US Department of Energy (DO
 E) sites that have been used to produce nuclear materials for defense\, in
 dustrial\, and medical purpose.  During several decades of processing\, lo
 w-level radioactive effluents were discharged at the site\, which have sub
 sequently migrated away from the disposal area. Remediation of the area is
  needed\; however\, remedial action requires a thorough understanding of t
 he contaminant behavior in this environment.\n\nIn this study\, the distri
 bution of contaminants in soils collected from the SRS F-area seepage basi
 n and down gradient from the source was quantified for U\, Pu\, Am\, and C
 m using radioanalytical and mass spectrometric techniques.  The results su
 ggest that there are two sources of U and three sources of Pu in this area
 .  In addition\, using published groundwater data\, Pu and Cm behavior in 
 the groundwater is proposed .  Also\, the partitioning of actinides to the
 se soils was studied using sequential extraction.  The results indicate a 
 source dependency for actinide partitioning in the soils.  This informatio
 n can be used by remediation engineers to design appropriate cleanup alter
 natives for the area.\n\nhttp://indico.cern.ch/contributionDisplay.py?cont
 ribId=60&sessionId=30&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=60&sessionId=30
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Study on Quadrivalent Chemical Species of Rutherfordium in Aqueous
  Solution by Means of TTA resin
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-61@cern.ch
DESCRIPTION:Speakers: Dr. YOKOYAMA\, Akihiko (Kanazawa University\, Japan)
 \nRutherfordium (Rf) has attracted a lot of attention in research on the c
 hemical properties of a superheavy element. For the purpose of its speciat
 ion in aqueous solution\, we aim to observe the chemical behavior of Rf by
  means of reversed-phase chromatography with a chelate extractant of 2-the
 noyltrifluoroacetone (TTA) as the stationary phase. It extracts quadrivale
 nt metal ions preferentially\, and\, that is\, it will make possible deter
 mination of a specific complex formation constant of Rf. \nPrior to the ex
 periments with Rf\, batch experiments of Zr and Hf were performed to deter
 mine the time to attain the chemical equilibrium on TTA-resin and the even
 tual distribution ratios. The resin was brought into contact with 88Zr and
  175Hf carrier-free atoms in the acid solutions of 9.5×10－5 – 0.10 M 
 HF / 0.1 M HNO3 and allowed to attain equilibration in a polypropylene tub
 e at room temperature. An aliquot of the aqueous phase was subjected to γ
 -ray spectrometry using a Ge detector. Similarly\, an off-line reversed-ph
 ase extraction chromatography of 88Zr and 175Hf was also performed in a te
 flon tube column (1.6 mmφ) or a micro-column (1.6 mmφ×7 mm) into which 
 the resin was filled. Then an on-line reversed-phase extraction chromatogr
 aphy was performed with 89mZr and 175Hf\, simultaneously produced in the 8
 9Y (p\, n) and 175Lu (p\, n) reactions\, respectively\, at the RIKEN K70 A
 VF Cyclotron. \nFinally\, the chemical system for the Rf experiment with A
 RCA (automated rapid chemistry apparatus) with the micro-columns was conne
 cted to the automated rapid α/SF detection system at the AVF cyclotron an
 d subjected to the experiment with 85Zr 169Hf\, and 261Rf isotopes produce
 d in the 18O-induced reaction with the targets of natGe\, natGa\, and 248C
 m\, respectively. Thus far we have succeeded in obtaining a preliminary α
 -spectrum of Rf nuclides transferred through a gas-jet system and passing 
 through the ARCA system. We are now ready to proceed to the further experi
 ments for the purpose of obtaining a better statistical data.\n\nhttp://in
 dico.cern.ch/contributionDisplay.py?contribId=61&sessionId=26&confId=18340
 5
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=61&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:SYNTHESIS AND X-RAY STUDY OF RADIUM METAPLUMBATE
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-258@cern.ch
DESCRIPTION:Speakers: BUTKALYUK\, Irina (S)\nThe report presents experimen
 tal results on the synthesis and properties study of radium- and lead-base
 d mixed oxide. Samples for examination were produced by high-temperature t
 reatment of mixed RaCO3/PbCO3. A mixture of 2.0 mg of RaCO3 and 5.0 mg of 
 PbCO3 was calcinated at 800°С for 8 hours in a stainless steel crucible.
  Resulted sample was studied by X-ray difractometry. In the X-ray pattern 
 15 reflexes of 43 registered ones were the strongest and referred to the p
 hase being an analog of BaPbO3 with a cubic perovskite structure. \nTaking
  into account potential contamination of radium plumbate with corrosion pr
 oduct coming from steel crucible\, the experiment was repeated with the us
 e of a platinum crucible. Sample of radium nitrate used in this run was pr
 eliminary purified by cation-exchange chromatography: the barium content b
 eing decreased to 100 g and the total amount of impurities Ca\, Fe\, Ba
 \, Al\, B\, Si were below 76 g.\nDuring the second experiment\, 2.9 mg 
 of RaCO3 and 4.6 mg of PbCO3 were calcinated at 800 °С for 20 hours in t
 he platinum crucible. The interpreted X-ray pattern showed the strongest r
 eflexes to belong to metal platinum that came to the sample as an impurity
 . The other group of intensive reflexes corresponds to the phase of cubic 
 RaPbO3. The X-ray pattern also demonstrated a group of 5 reflexes close in
  the location and relation of their intensity to BaPtO2.38 phase reflexes.
  More probably\, this group of reflexes corresponds to radium platinate Ra
 PtO3-x produced while radium reacts with the crucible material. \nBased on
  supposition of RaPbO3 formation\, the interplanar space values were calcu
 lated as well as crystalline lattice parameter (а=4.303 Å) and crystallo
 graphic density (ρ=10.0 g/cm3).\n\nhttp://indico.cern.ch/contributionDisp
 lay.py?contribId=258&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=258&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - The unique chemical and physical properties of t
 he heaviest elements in the Periodic Table
DTSTART;VALUE=DATE-TIME:20120918T070000Z
DTEND;VALUE=DATE-TIME:20120918T073000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-63@cern.ch
DESCRIPTION:Speakers: Prof. KRATZ\, Jens Volker (Universität Mainz\, Germ
 any)\nThe unique role of the heaviest elements in chemical and physical sc
 iences is discussed. With the actinide series (Z = 90 – 103) and the sup
 eractinide series (Z = 122 – 155)\, the heaviest elements have significa
 ntly shaped the architecture of the Periodic Table of the elements. Relati
 vistic effects in the electron shells of the heaviest elements change the 
 chemical properties in a given group in a non-linear fashion. Relativistic
 ally stabilized sub-shell closures give rise to a new category of elements
  in the Periodic Table: volatile metals. The prototype for this property i
 s element 114 which\, due to the relativistic stabilization of its 7s27p1/
 22 electron configuration\, is volatile in its elementary state\, but\, in
  contrast to a noble gas\, exhibits a marked metal-metal interaction with 
 a gold surface at room temperature. Nuclear shell effects dominate the phy
 sical properties of the transuranium elements. These give rise to superdef
 ormed shape isomers (fission isomers) in the actinides (U – Bk). Superhe
 avy elements (Z ≥ 104) owe their existence solely to nuclear shell effec
 ts at N = 152\, 162\, and 184. At this time\, a building lot is the locati
 on of the next spherical proton shell closure as there is evidence that th
 e center of the “island of stability” is not at Z = 114. This needs ur
 gently further theoretical and experimental efforts. The cross sections fo
 r the syntheses of elements 119 and 120 will give us important information
  on the “upper end of the Periodic Table of the elements”.\n\nhttp://i
 ndico.cern.ch/contributionDisplay.py?contribId=63&sessionId=20&confId=1834
 05
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=63&sessionId=20
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Accelerator-based Alternative Tc-99m production: EMPIRE 3.1 theore
 tical simulations of cross sections for Mo(p\,X) reactions and comparison 
 with literature experimental data
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-64@cern.ch
DESCRIPTION:Speakers: Dr. ESPOSITO\, Juan (INFN-Laboratori Nazionali di Le
 gnaro\, Italy)\nTechnetium 99 metastable is the most important and widely 
 used radionuclide in nuclear medicine for over 80% of all diagnostic proce
 dures. Recent shortage of this isotope prompted the international scientif
 ic community to ask for investigations on new possible production routes. 
 As possible alternatives to the current reactor-based 235U(n\,f)99Mo→99m
 Tc scheme\, accelerator-based methods have been considered. In this work\,
  a feasibility study for the production of 99mTc from irradiation with pro
 tons on natural and highly enriched molybdenum targets has been performed.
  In the framework of INFN LARAMED (LAboratory of RAdionuclide for MEDicine
 ) project currently under way at Legnaro labs\, theoretical simulations of
  excitation functions and yields have\, in particular been studied for nat
 Mo(p\,X)and 100Mo(p\,X) reactions in the 5-35 MeV proton energy range. In 
 addition\, a review of all existing experimental data has been collected a
 nd compared with the simulations. Theoretical calculations were carried ou
 t using the new EMPIRE 3.1 (Rivoli Release) nuclear code\, a modular syste
 m of  nuclear models whose new features permit to evaluate the population 
 probability of isomer states. Preliminary results of simulations have show
 n good agreement with experimental data. Estimation for the production of 
 other radioactive and stable nuclides together with 99mTc has been calcula
 ted and considered an important discriminator for the feasibility of the p
 roduction route since the presence of other harmful nuclides in the final 
 product could affect the diagnostic outcome and radiation dosimetry in hum
 an studies.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=64&s
 essionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=64&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Preservation of Cultural Heritage by Radioanalyt
 ical Techniques
DTSTART;VALUE=DATE-TIME:20120921T100000Z
DTEND;VALUE=DATE-TIME:20120921T102000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-65@cern.ch
DESCRIPTION:Speakers: Prof. NAVARRETE\, Manuel (Faculty of Chemistry\, Nat
 ional University of Mexico\, Mexico)\nAncient raw materials are degraded a
 nd finally detroyed\, mainly by humidity taking up dissolved salts from so
 il\, which are deposited on walls surface breaking plasters and material s
 tructure as time goes by. This process is added to environment humidity an
 d temperature changes\, but in any case is proportional to porosity materi
 als. This is why\, such materials as limestone\, sand stone and volcanic s
 tones are most difficult to preserve that feldspar or marble\, for example
 . One easy way to measure the relative porosity of any stuff used in the p
 ast as raw material\, is to cut samples in the shape of small prisms\, to 
 weigh each and to place their basis on a layer about 3 mm deep of a Na-22 
 (0.01 microcuries/ml)radioactive solution during 5 minutes. Once dry out a
 nd conditioned in test tubes or small plastic bags\, annihilation gamma ra
 ys are detected in a low background\, well type 3x3'' NaI(Tl) scintillatio
 n detector\, during suitable time to accumulate as much counts as possible
 . Counts per time unit (seconds or minutes) and per weight (grams of stuff
 ) are a relative measurement of the material porosity\, which is always pr
 oportional to its absorbing power. So\, when other pieces of same stuff ar
 e cut in similar way and put in contact with a warm solution (60º-80ºC)o
 f french gelatin (5%)\, plus potassium sorbate (2.5%) and sodium benzoate 
 (2.5%)\, warm solution tends to occupy the small air volumes of pores and 
 channels quicker that if it were cold water. About 3 hours later\, at room
  temperature\, when the material looks little thicker and brilliant\, it i
 s added a concentrate solution (38%)of formaldehyde\, about 10-15% of volu
 me of gelatine employed\, in order to get tougher and almost quite insolub
 le in water gelatin\, as well as quite unsuitable to create some organic c
 ultures in it\, since potassium sorbate and sodium benzoate are used as fo
 od conservatives\, and formaldehyde is used to preserve corpses. When thes
 e pieces are treated with radioactive solution in the same way that previo
 us ones\, detection counts per time and weight units are reduced dramatica
 lly by factors at inverse proportion than those obtained with no gelatin. 
 Also\, it is a reversible process\, since it is possible to dissolve the g
 elatin just by washing with warm water (60º-80ºC)while it resists perfec
 tly washing with cold water (20º-30ºC). Based on these laboratory result
 s some prehispanic pieces have been treated in Mexico quite successfully\,
  with no problem at all during 3-8 years. This paper presents these result
 s and proposes to perform the procedure in some other mankind's prides suc
 h as Haga Sophia\, Xian's warriors\, Mithraeum in Sutri\, Italy\, Borobudu
 r in Java island\, Indonesia\, Sukhothai\, Thailand\, Ajanta Caves and Mal
 uti Temple in India\, and many others all over the world.\n\nhttp://indico
 .cern.ch/contributionDisplay.py?contribId=65&sessionId=31&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=65&sessionId=31
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Development of <sup>44</sup>Sc production for 
 radiopharmaceutical applications
DTSTART;VALUE=DATE-TIME:20120917T144000Z
DTEND;VALUE=DATE-TIME:20120917T145500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-179@cern.ch
DESCRIPTION:Speakers: Mrs. BUNKA\, Maruta (Laboratory of Radiochemistry an
 d Environmental Chemistry\, Villigen PSI\, Switzerland)\nIntroduction: 44S
 c with a half-life of 3\,97 h and a positron branching of 94 % is a promis
 ing nuclide for novel PET-radiopharmaceuticals. With an oxidation state of
  +3 44Sc may be used for radiolabeling of biomolecules with chelators esta
 blished for coordination of lanthanides such as 177Lu and for other clinic
 ally employed radionuclides such as 90Y\, 111In or 68Ga. At the Paul Scher
 rer Institute we are evaluating and optimizing the production of 44Sc for 
 radiopharmaceutical applications. \n\nMethods: 44Sc was produced from a 44
 CaCO3 solid target at a cyclotron with protons up to 15 MeV (30-50 μA\, 2
 0-40 min). For the isolation of 44Sc from the target material extraction c
 hromatography and cation exchange chromatography were employed. After the 
 isolation and purification of 44Sc\, radiolabeling reactions were investig
 ated using different molar amounts of a DOTA-folate conjugate.\n\nResults:
  The irradiation yield was 150 – 200 MBq/μAh with \n\nhttp://indico.cer
 n.ch/contributionDisplay.py?contribId=179&sessionId=17&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=179&sessionId=1
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - Recent Advances in Superheavy Element Research
DTSTART;VALUE=DATE-TIME:20120918T060000Z
DTEND;VALUE=DATE-TIME:20120918T063000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-178@cern.ch
DESCRIPTION:Speakers: Prof. TÜRLER\, Andreas (Laboratory of Radiochemistr
 y and Environmental Chemistry\, Paul Scherrer Institute & Bern University\
 , Switzerland)\nWith the recent synthesis of element 117\, the 8th row of 
 the Periodic Table of the Elements is complete. Also\, the elements with a
 tomic numbers 114 and 116 have now officially been named Flerovium and Liv
 ermorium by IUPAC. Significant progress has not only been achieved in synt
 hesizing new elements\, but also in their chemical characterization. In my
  contribution I will give an overview of the status of the experimental wo
 rk on the attempted synthesis of elements beyond Z=118 and then review the
  gas-phase chemistry of Hassium\, Copernicium\, and Flerovium and compare 
 the results with theoretical predictions. Then I will discuss latest devel
 opments concerning chemistry experiments with pre-separated heavy element 
 beams\, that hold promise to chemically investigate so far not studied ele
 ments in the Periodic Table\, which leads to an outlook about the near and
  far future of superheavy element research.\n\nhttp://indico.cern.ch/contr
 ibutionDisplay.py?contribId=178&sessionId=20&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=178&sessionId=2
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Solution reactors for production of Mo-99 and Sr
 -89 (via Kr-89)
DTSTART;VALUE=DATE-TIME:20120918T141000Z
DTEND;VALUE=DATE-TIME:20120918T143000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-252@cern.ch
DESCRIPTION:Speakers: Dr. PAVSHUK\, Vladimir A. (Russian Research Center 
 “Kurchatov Institute”\, Russia)\nMolybdenum-99 is the most important a
 nd widely used medical radionuclide which production in required quantitie
 s is possible only by fission products of Uraniun-235. In clinical practic
 e the share of Mo-99 usage reaches approximately 80% of the total amount o
 f radioisotope diagnostic procedures in the world. Strontium-89 is used fo
 r oncology and anesthesia and is capable of replacing painkilling drugs. I
 nnovative technologies for production of Мо-99 and Sr-89 using solution 
 reactors have been developed in RRC “Kurchatov Institute”. These techn
 ologies reduce the required reactor power by approximately 100 times\, dec
 rease amount of radioactive waste and are suitable for low-enriched uraniu
 m fuel in comparison with conventional production methods. The technologie
 s have been experimentally proven and refined using 20-kW solution reactor
  “Argus” where the isotope samples of required quality have been produ
 ced. Mo-99 has been extracted from irradiated soluble nuclear fuel by pump
 ing the solution though a sorption column. Accumulation of the isotope occ
 urs during 5-day reactor operation at nominal power while the extraction i
 s done after the reactor shutdown. Sr-89 is obtained from Kr-89 which is e
 vaporated during reactor operation. \nThe achieved results lead to further
  plans including development of Мо-99 and Sr-89 production line using 15
 0-kW nuclear reactor.\n\nhttp://indico.cern.ch/contributionDisplay.py?cont
 ribId=252&sessionId=19&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=252&sessionId=1
 9&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:The LARAMED project at INFN Legnaro National labs
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-69@cern.ch
DESCRIPTION:Speakers: Dr. ESPOSITO\, Juan (INFN (Istituto Nazionale di Fis
 ica Nucleare))\nIn the framework of INFN SPES (Selective Production of Exo
 tic nuclear Species) special project\, aimed the new frontier of nuclear p
 hysics research of unstable nuclei\, the creation of a center for innovati
 ve radionuclides production for radiopharmaceuticals is also pursued. Such
  a dedicated project\, called LARAMED (Laboratory of RAdionuclides for MED
 cine) will take advantage of the high performance SPES proton cyclotron (7
 0 MeV\, 750 microamps) which will be available at INFN LNL in the next com
 ing years. The main goals of LARAMED project cover different topics\, rang
 ing from nuclear physics (excitation function experimental measurements)\,
  to engineering aspects (high power production targets) and radiochemistry
  issues (improvements of separation purification techniques). It will be a
  first step towards interdisciplinary researches directed to innovative ra
 dionuclides production\, such as 64/67Cu\, 82Sr/82Rb\, 68Ge/68Ga which are
  of interest in nuclear medicine for diagnostic and therapy applications. 
 Moreover studies and efforts are currently underway to start alternative a
 ccelerator-driven direct production of 99Mo/ 99mTc\, (the most important a
 nd widely used radionuclide in nuclear medicine so far) according to pharm
 acopeia GMP rules\, from 100Mo(p\,xn) reactions. The goal is to get enough
  production to fulfill the hospital needs in north-east of Italy. Such res
 earches will be a possible evolution of activities at Legnaro labs in the 
 next years\, which are a recognized excellence center in nuclear physics a
 nd nuclear astrophysics researches\, towards a system where basic science 
 and technological applications coexist and provide synergy to each other.\
 n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=69&sessionId=26&
 confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=69&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - Future prospects in diagnostic and therapeutic n
 uclear medicine
DTSTART;VALUE=DATE-TIME:20120917T080000Z
DTEND;VALUE=DATE-TIME:20120917T083000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-250@cern.ch
DESCRIPTION:Speakers: Prof. CHATAL\, Jean-François (GIP ARRONAX\, France)
 \nFor the last two decades a technological revolution has deeply changed t
 he field of application of nuclear medicine. Today PET/CT imaging using 18
 F-Fluorodeoxyglucose (FDG) is considered as the standard imaging technique
  in oncology for tumor staging\, detection of recurrence and early evaluat
 ion of response to treatment. PET/MRI could shortly become the standard im
 aging technique in neurology. Molecular radiotherapy has also made great p
 rogress with the rapid development of radioimmunotherapy (RIT) and radiope
 ptide therapy (RPT).\nFor diagnostic imaging\, FDG radiopharmaceutical is 
 the only one to be used in routine practice but a lot of fluorinated compo
 unds are currently clinically evaluated and some of them will be approved 
 in the coming years. In oncology several fluorinated radiopharmaceuticals\
 , evaluated in ongoing clinical studies\, will allow to visualize tumor fu
 nctions such as apoptosis\, tumor neo-angiogenesis\, hypoxia etc… and th
 en to better determine optimal therapeutic strategy. In neurology FDA appr
 oved in 2012 Amyvid™ (Florbetapir F 18 Injection) for use in patients be
 ing evaluated for Alzheimer's disease and other causes of cognitive declin
 e. Amyvid is thus the first radioactive diagnostic agent approved for PET 
 imaging of beta-amyloid neuritic plaques in the brain.\nHowever the use of
  fluorine-18 for PET imaging has some limitations and innovative positron-
 emitting radionuclides are needed. Among them\, gallium-68\, obtained from
  a germanium-68/gallium-68 generator and copper-64 with relatively short h
 alf-lives and zirconium-89 and iodine-124 with longer half-lives have been
  the most extentively studied radionuclides and will be routinely used in 
 the next years.\nFor molecular radiotherapy\, efficacy of RIT and RPT has 
 been clearly documented in some clinical settings  and new radiopeptides a
 nd radioconjugates labeled with lutétium-177\, yttrium-90 and perhaps cop
 per-67 will likely be approved for treatment of a panel of cancers especia
 lly in the most favorable situation of disseminated microscopic residual d
 isease. Finally the use of  alpha particle-emitting radionuclides such as 
 astatine-211\, lead-212\, bismuth-213 or actinium-225 will be developed fo
 r treatment of clusters of malignant cells and isolated tumor cells at the
  very early stage of cancer progression.\n\nhttp://indico.cern.ch/contribu
 tionDisplay.py?contribId=250&sessionId=15&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=250&sessionId=1
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Iodine - 129 in water samples from Germany
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-174@cern.ch
DESCRIPTION:Speakers: Ms. SCHWINGER\, Mareike (Leibniz Universität Hannov
 er\, Germany)\nThe natural abundance of 129I has been changed through anth
 ropogenic activities\, such as nuclear weapon testing\, nuclear accidents 
 and reprocessing of nuclear fuel. Mainly as a con-sequence of continuous r
 eleases of 129I from the nuclear reprocessing facilities in La Hague (Fran
 ce) and Sellafield (UK)\, 129I is in a state of disequilibrium in all envi
 ronmental compart-ments in Western Europe.\nIt is emitted in gaseous and l
 iquid form\, with most of it as liquid waste which flows into the North Se
 a [1]. From there it is reemitted to and distributed in the atmosphere\, a
 nd precipitates as wet or dry deposition [2].\nIn this project we analyse 
 precipitation samples from 10 sampling locations and river water samples f
 rom 15 sampling locations all over Germany. The concentrations of 129I and
  127I are determined\, as well as their isotopic ratio. \nIodine is extrac
 ted from the water by ion exchange resin. 127I is analysed using inductive
 ly-coupled plasma mass spectrometry (ICP-MS) and the isotopic ratio is det
 ermined via accel-erated mass spectrometry (AMS). \nResults of the 127I an
 alyses reveal slightly higher concentrations for the river water samples (
 1.7 to 15.9 ng/g) than for the rain water samples (0.6 to 9.8 ng/g). Conce
 ntrations of 129I range between 17 to 2000 fg/kg (rain water) and between 
 17 to 350 fg/kg (river water)\, respectively. For the precipitation sample
 s (14∙10-9 to 650∙10-9)\, as well as for the river water samples (3∙
 10-9 to 40∙10-9)\, the 129I/127I ratios are at least 3 orders of magnitu
 de higher than the natural equilibrium isotopic ratio of 1.5∙10-12 [2].\
 n\n[1] J.M. Gómez-Guzmán et al. (2012) Atmospheric Environment 56\, 26-3
 2. [2] R. Michel et al. (2012) Science of the Total Environment 419\, 151-
 169.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=174&session
 Id=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=174&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Overview of PET radionuclide production methods.
DTSTART;VALUE=DATE-TIME:20120919T071000Z
DTEND;VALUE=DATE-TIME:20120919T073000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-256@cern.ch
DESCRIPTION:Speakers: Prof. CLARK\, John C (University of Edinburgh\, UK)\
 nPositron Emission Tomography (PET) Imaging requires radiolabelled materia
 ls (biomarkers) incorporating radionuclides that decay by positron emissio
 n.\nThey are largely neutron deficient and are made with a  charged partic
 le accelerator usually a cyclotron.\nThe most important radionuclides are 
 18F\, 11C\, 15O and 13N although an increasing interest is being seen in t
 he radio metals in particular 68Ga 64Cu and 89Zr.\nIn order to achieve use
 able production yields of any radionuclide certain criteria have to me met
  especially the nuclear reaction cross sections at the charged particle en
 ergies available with a typical PET cyclotron with a proton energy of 10 t
 o 20 Mev. \nAvailable charged particle beam current will determine the int
 ensity of the charged particle irradiation and hence the number of useful 
 nuclear reactions achieved.\nHowever many other factors come into play in 
 the practical use of cyclotrons and their associated targets to achieve ra
 dionuclide intermediates suitable for incorporation into PET biomarkers.\n
 The two most important radionuclides used in the Medical applications of P
 ET are fluorine-18 and carbon-11 and aspects of their effective production
  will be discussed in detail.\nReference will be made to the methods of pr
 oduction of the other less widely used PET radionuclides without significa
 ntly overlapping with other presentations at this meeting.\n\nhttp://indic
 o.cern.ch/contributionDisplay.py?contribId=256&sessionId=23&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=256&sessionId=2
 3&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:NORMA: A new PGAI-NT setup at the Budapest Research Reactor
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-257@cern.ch
DESCRIPTION:Speakers: Dr. SZENTMIKLÓSI\, László (Centre for Energy Rese
 arch\, Hungarian Academy of Sciences)\nEfforts are being made at laborator
 ies worldwide to develop Prompt Gamma Activation Analysis (PGAA) towards a
  position-sensitive technique. It was proven earlier that the complete sca
 nning with a few-mm-resolution is only practical on small objects due to c
 onstrains of experiment time and neutron flux. A feasible alternative is t
 he combination of neutron radiography with prompt gamma activation analysi
 s. Radiography\, or even a full tomography of the complex sample\, as a fi
 rst step\, can be completed in minutes\, but often provides enough informa
 tion to set up regions of interests inside the sample. The detailed elemen
 t analysis by PGAA is carried out then only at these spots\, saving substa
 ntial beam time. This novel combination of methods is best used for real s
 amples which consist of a few homogeneous parts. \n\nThe first ever pilot 
 instrument for this purpose was installed at the Budapest Research Reactor
  in 2007 and has been presented at the NRC7 conference. The technique prov
 ed its usefulness and raised enough interest in the user community to cont
 inue the efforts. Based on these experiences the first permanent radiograp
 hy-driven PGAI facility\, NORMA (Neutron Optics and Radiation Measurement 
 for element Analysis) was constructed and put into operation in the first 
 months of 2012. \n\nIts specifications supersede the pilot setup in every 
 aspect. The sample chamber has now dimensions of 20×20×20 cm^3. By remov
 ing one or more side panels\, larger objects up to 5 kg weight could be an
 alyzed (such as a sword\, vase\, stones\, etc.). Samples can also be loade
 d to the chamber manually from the top side. The positioning table has a n
 ominal travel distance of 200 mm. The gamma radiation is detected with a C
 ompton suppressed system\, that consists of a central Canberra GR2318/S HP
 Ge detector surrounded by a Bismuth Germanate (BGO) scintillator made by S
 cionix. The cylindrical and exchangeable lead collimators can be mounted i
 nto a socket of the 10-cm thick lead shielding. The gamma events are colle
 cted with a Canberra DSP-2060 digital signal processor\, in anti-Compton m
 ode. The imaging system comprises a 100 um thick Li-6/ZnS scintillator\, a
  silver-free quartz mirror set in 45 degree to the neutron beam and a cool
 ed ANDOR iKon-M CCD camera (16-bit ADC and 1024×1024 pixel resolution)\, 
 mounted to a light tight aluminum housing. Integrated data acquisition sof
 tware operates the moving table\, the gamma-ray spectrometer and the camer
 a.\n\nThe commissioning has just recently been completed\, and the facilit
 y became open to the international user community through the EU FP7 NMI3\
 , CHARISMA and EFNUDAT access programs. The first results of this non-dest
 ructive technique will be presented here from various fields of applicatio
 ns\, such as archaeometry\, safeguards and material science.\n\nhttp://ind
 ico.cern.ch/contributionDisplay.py?contribId=257&sessionId=26&confId=18340
 5
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=257&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - On the road from Radiopharmacy to Molecular Imag
 ing: the fundamental role of Technetium and Rhenium Chemistry
DTSTART;VALUE=DATE-TIME:20120917T090000Z
DTEND;VALUE=DATE-TIME:20120917T092000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-171@cern.ch
DESCRIPTION:Speakers: Prof. ALBERTO\, Roger (University of Zurich\, Switze
 rland)\nImaging and visualization of molecular events on the cellular and 
 subcellular level requires the design and the syntheses of highly specific
  compounds which have to to accumulate at desired target sites but should 
 be rapidly cleared from non-targeted organs. Visualization must take place
  at the living intact subject and the patient.[1] This makes radiolabeled 
 compounds a priority modality for imaging. The design of highly specific c
 ompounds does not only concern the biological carrier of the imaging agent
  as often believed\, but the label in particular. Consequently\, the label
  cannot be considered as “just a tag” any longer\, but its properties 
 and opportunities have to be integrated in the entire design. Transition m
 etals such as technetium and rhenium (and others) are predestinated to ass
 ume roles of structure and function essential molecules due to their inher
 ent diversity of bonds and ligands. Drug finding and development needs\, t
 hus\, exploration of fundamental chemistry with application in mind. The p
 resentation will outline with examples the importance of fundamental chemi
 stry of technetium and rhenium for applications of concepts and agents. A 
 focus will be put on cyclopentadienyl complexes to emphasize the 3D-space 
 occupation concept. Aspects of the theranostic concept in which technetium
  complexes are used for imaging and rhenium homologous for therapy will be
  presented[2] as well as the integration of Tc and Re in very small biolog
 ical molecules. \n\n[1]	S. Achilefu\, Chem. Rev. 2010\, 110\, 2575-2578.\n
 [2]	D. Can\, B. Spingler\, P. Schmutz\, F. Mendes\, F. Raposinho\, F. Cart
 a\, A. Innocenti\, I. Santos\, C. T. Supuran\, R. Alberto\, Angew. Chem. I
 nt. Ed. 2012\, 51\, 3354-3357.\n\nhttp://indico.cern.ch/contributionDispla
 y.py?contribId=171&sessionId=15&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=171&sessionId=1
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Interaction of Cm(III) with human serum transferrin studied by Tim
 e-Resolved Laser Fluorescence Spectroscopy (TRLFS)
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-106@cern.ch
DESCRIPTION:Speakers: BAUER\, Nicole (Institute for Nuclear Waste Disposal
 \, Karlsruhe Institute of Technology\, Germany)\nIn case of an accidental 
 release of radionuclides to the environment actinides can cause a serious 
 health risk upon incorporation. There is only deficient knowledge about th
 e chemical behavior and toxicity of actinides in man. With regard to the d
 evelopment of potential decontamination therapies\, a detailed understandi
 ng of the mechanisms of relevant biochemical reactions is necessary.[1] Hu
 man serum transferrin is an iron carrier protein in the blood. It is folde
 d into two lobes housing the metal binding sites for Fe(III).[2] In the no
 rmal blood serum\, only 30 % of transferrin is saturated with iron\, which
  indicates that there is a high capacity for the complexation of other met
 al ions.\nHuman serum transferrin is found to be contaminated by EDTA. In 
 the present work a purification process was developed using size exclusion
  chromatography and centrifugal filters. After purification the complexati
 on of Cm(III) with transferrin is studied at various pH values and transfe
 rrin concentrations by time-resolved laser fluorescence spectroscopy (TRLF
 S). The results show that two different species are formed. In the pH rang
 e from 6.3 to 7.7 the spectra are dominated by the Cm(III) transferrin spe
 cies I\, displaying an emission band at 600.0 nm. The fluorescence lifetim
 e of 97 μs correlates with a coordination of six water molecules indicati
 ng a threefold coordination mode with the protein and/or a synergistic ani
 on such as hydroxid or carbonate at the binding site.[3] Above pH 7.7 the 
 Cm(III) transferrin species II with an emission band at 620.3 nm is formed
 . The extraordinary bathochromic shift of 26.6 nm relative to the emission
  band of the Cm(III) aquo ion and the fluorescence lifetime of 221 μs con
 firm incorporation of Cm(III) at the transferrin binding site resulting in
  a 4-fold coordination via amino acid groups (Asp-63\, Tyr-95\, Tyr-188 an
 d His-249) of the protein. The remaining coordination sites of Cm(III) are
  occupied by synergistic anions and water molecules.\n\n[1] A. E. V. Gorde
 n\, J. D. Xu\, K. N. Raymond\, P. Durbin\, Chem Rev \n    2003\, 103\, 420
 7-4282.\n[2] H. Z. Sun\, H. Y. Li\, P. J. Sadler\, Chem Rev 1999\, 99\, 28
 17-2842.\n[3] T. Kimura\, Choppin\, G. R.\, J Alloy Compd 1994\, 213/214\,
  313-317.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=106&se
 ssionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=106&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Enhancing the dynamic range for high boron con
 centrations in low neutron capture cross-section matrices with Prompt Gamm
 a Activation Analysis
DTSTART;VALUE=DATE-TIME:20120920T082500Z
DTEND;VALUE=DATE-TIME:20120920T084000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-175@cern.ch
DESCRIPTION:Speakers: Mr. SOELLRADL\, Stefan (Paul Scherrer Institute & Un
 iversität Bern\, Switzerland)\nAt the beam line of Prompt Gamma Activatio
 n Analysis (PGAA)\, one of the most powerful cold neutron beams in the wor
 ld is available for experiments with neutrons. It offers unique possibilit
 ies to improve the detection limits\, counting statistics and allows even 
 the detection of trace elements and extremely small samples.\n\nProblems a
 rise\, if relatively high amounts of high-cross-section elements like boro
 n are to be detected in a matrix of elements with relatively low neutron c
 apture cross-sections such as aluminum or silicon. In these cases the high
 -purity germanium detector (HPGe) can be saturated even when using small s
 ample masses. For the case that the sample mass or the neutron flux is red
 uced to lower the count rates\, the dynamic ranges of the peak areas do no
 t change. The idea was to suppress the low energy gamma radiation mainly f
 rom boron more than the higher energy one from matrix elements using Pb sh
 eets with different thicknesses. The efficiencies without lead attenuator\
 , with 5mm and 10mm of lead in front of the detector were determined and s
 amples with different nominal compositions made of milled powder mixtures 
 of SiO2\, Al2O3\, and H3BO3 were analyzed using the appropriate efficienci
 es.\n\nThe technical details of the method and the results of the first ex
 periments will be presented.\n\nhttp://indico.cern.ch/contributionDisplay.
 py?contribId=175&sessionId=27&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=175&sessionId=2
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Half lives of nuclides for geological use: 2012 
 evaluations for <sup>87</sup>Rb\, <sup>235</sup>U and <sup>234</sup>U
DTSTART;VALUE=DATE-TIME:20120918T101000Z
DTEND;VALUE=DATE-TIME:20120918T103000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-253@cern.ch
DESCRIPTION:Speakers: Prof. VILLA\, Igor M (Universität Bern\, Switzerlan
 d\; Università Milano Bicocca\, Italy)\nThe IUPAC-IUGS joint Task Group 
 “Isotopes in Gesciences”\, TGIG\, has evaluated the published measurem
 ent results for the decay constant (i.e. half life) of 87Rb and updated th
 ose of 235U and 234U relative to that of 238U. A significant part of our e
 valuation was the effort to follow strict metrological criteria (VIM\, 201
 2) in our assessment of the measurement uncertainties according to GUM (20
 08).\nThe 87Rb half life was estimated by two groups using totally indepen
 dent approaches. Nebel et al. (2011) compared Rb-Sr and U-Pb ages of diffe
 rent minerals\, whose geological context suggests contemporaneity. This ap
 proach\, which also applies to the comparison between 238U-206Pb and 235U-
 207Pb ages mentioned below\, assumes that certain natural samples behave 
 “ideally”\, i.e. all the relevant ages are expected a priori to be equ
 al. This assumption is only as good as the independent control on the samp
 les’ petrology\, and it is possible to underestimate systematic bias. Ro
 tenberg et al. (2012) measured the radiogenic 87Sr accumulated in a batch 
 of Sr-free Rb salt after 35 years. This approach relies on having performe
 d precise and accurate measurements of the concentration and isotopic comp
 osition of the Sr present in the RbClO4 at the time of crystallisation. Th
 e two sets of experiments yield indistin¬guishable results\, which is a g
 ood indication that systematic biases were either coincidentally of the sa
 me magnitude and direction in two radically different experimental designs
 \, or negligible altogether. The resulting best estimates are λ87 = (1.39
 5 ± 0.002) x 10-11 a-1 (1s uncertainty)\, t1/2 = 49.7 ± 0.1 Ga.\nThe hal
 f life of 235U\, which we had presented last year at the INCC congress (Vi
 lla et al.\, 2011\, and references therein)\, has been slightly revised. I
 t was brought to the attention of the Task Group that some workers reporte
 d a mass-independent fractionation of incompletely understood origin that 
 affects odd- and even-mass isotopes in a different way (e.g. Amelin et al.
 \, 2005). Moreover\, recent reports on N(238U)/N(235U) number ratio measur
 ements in the same zircon samples used for geochronology (Hiess et al.\, 2
 012) indicate an individually variable number ratio\, on average lower by 
 (0.031 ± 0.011) % relative to the previously assumed value of 137.88. Inc
 luding both effects into the 235U half life re-evaluation gives t1/2 = 703
 .41 ± 0.19) Ma (1s uncertainty)\, λ235 = 0.98540 ± 0.00027 Ga-1.\nThese
  two effects do not modify the 234U half life relative to our 2011 assessm
 ent: t1/2 = 245.44 ± 0.16 ka (1s uncertainty)\, corresponding to λ234 = 
 2.8241 ± 0.0018 Ma-1. \n\nAmelin Y.\, Davis D.W.\, Davis W.J. (2005) Deco
 upled fractionation of even- and odd-mass isotopes of Pb in TIMS. Geochim.
  Cosmochim. Acta 69\, Abstract Supplement\, A215.\nGUM (2008) Guide to the
  expression of uncertainty in measurement. www.bipm.org/en/publications/gu
 ides/gum.html\nHiess J.\, Condon D.J.\, McLean N.\, Noble S.R. (2012) 238U
 /235U systematics in terrestrial U-bearing minerals. Science 335\, 1610-16
 14.\nNebel O.\, Scherer E.E.\, Mezger K. (2011) Evaluation of the 87Rb dec
 ay constant by age comparison against the U-Pb system. Earth Planet. Sci. 
 Lett. 301\, 1-8.\nRotenberg E.\, Davis D.W.\, Amelin Y.\, Ghosh S.\,  Berg
 quist B.A. (2012) Determination of the decay-constant of 87Rb by laborator
 y accumulation of 87Sr. Geochim. Cosmochim. Acta\, 85\, 41-57.\nVilla I.M.
 \, Bonardi M.L.\, De Bièvre P.\, Holden N.E.\, Renne P.R.\, 2011. Half-li
 ves of nuclides for geological use: 2011 evaluations for 235U and 234U. Ab
 stract\, 3rd International Nuclear Chemistry Congress\, Palermo.\nVIM (201
 2) The International Vocabulary of metrology – Basic and general concept
 s and associated terms\, 3rd edition\, JCGM 200:2012\, http://www.bipm.org
 /vim\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=253&session
 Id=21&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=253&sessionId=2
 1&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Complexation of Cm(III) with 2\,6-bis(5-(2\,2-
 dimethylpropyl)-1H-pyrazol-3-yl)pyridine (C5-BPP) studied by time-resolved
  laser fluorescence spectroscopy
DTSTART;VALUE=DATE-TIME:20120919T111500Z
DTEND;VALUE=DATE-TIME:20120919T113000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-107@cern.ch
DESCRIPTION:Speakers: BREMER\, Antje (Institute for Nuclear Waste Disposal
  - Karlsruhe Institute of Technology\, Geramany)\nReducing the long-term r
 adiotoxicity and heat load of spent nuclear fuel by separating long-lived 
 radionuclides and converting them into shorter lived or stable nuclides by
  fast neutron induced fission reactions is the aim of the so called partit
 ioning and transmutation strategy (P&T).[1] Key step is the separation of 
 the trivalent actinides Am(III) and Cm(III) from the trivalent lanthanides
  in the SANEX process. Due to the great chemical similarity of these metal
  ions\, an efficient separation is very challenging. Alkylated 2\,6-bis(1\
 ,2\,4-triazin-3-yl)pyridines (BTPs) belong to the most promising extractin
 g agents.[2] Although a multitude of BTP-type ligands has been synthesized
 \, the molecular reason for the high selectivity of these soft N-donor lig
 ands is not fully understood. To gain a better understanding\, further inv
 estigations on the complexation of An(III) and Ln(III) with BTP-type ligan
 ds with systematic variations in the aromatic system are of particular int
 erest. \nIn the present work\, the complexation of Cm(III) with 2\,6-bis(5
 -(2\,2-dimethylpropyl)-1H-pyrazol-3-yl)pyridine (C5-BPP) in methanol is in
 vestigated by TRLFS. Time-resolved laser fluorescence spectroscopy (TRLFS)
  is a very sensitive spectroscopic method which makes it possible to follo
 w the complex formation of fluorescing ions like Cm(III) in solution.[3] S
 pectroscopic parameters like position and shape of an emission band provid
 e information on the number and the type of coordinating ligands. For the 
 Cm(III) complexation with C5-BPP\, three different species\, the 1:1-\, 1:
 2- and 1:3-complex\, with emission bands at 603.7 nm\, 607.7 nm\, and 611.
 6 nm\, respectively\, are found. The species distributions for various lig
 and concentrations are determined and stability constants are derived (log
  K03 = 14.8). As extraction from nitric acid solutions with the C5-BPP lig
 and is only possible in the presence of a lipophilic anion\, the complexat
 ion of Cm(III) with C5-BPP and 2-bromohexanoic acid is investigated. It is
  found\, that 2-bromohexanoate ions are coordinated to the metal ion at lo
 w C5-BPP concentrations and are successively replaced by the N-donor ligan
 d in the inner coordination sphere.\n\n\n[1] Actinide and Fission Product 
 Partitioning and Transmutation\, Status and Assessment Report\, OECD Nucle
 ar Energy Agency\, 1999. [2] a) Z. Kolarik\, U. Müllich\, F. Gassner\, So
 lvent Extr. Ion Exch. 1999\, 17\, 1155-1170. b) S. Trumm\, A. Geist\, P. J
 . Panak\, Th. Fanghänel\, Solv. Extr. Ion Exch. 2011\, 29\, 213-229. [3] 
 R. Klenze\, J. I. Kim\, H. Wimmer\, Radiochim. Acta 1991\, 52/53\, 97-103.
 \n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=107&sessionId=2
 4&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=107&sessionId=2
 4&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Iodine-129 and iodine-127 in soils from Germany
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-182@cern.ch
DESCRIPTION:Speakers: Dr. RIEBE\, Beate (IRS / Leiniz Universitaet Hannove
 r\, Germany)\nThe environmental abundance of 129I has been changed substan
 tially\, mainly as a consequence of the 129I releases from European reproc
 essing plants [1\, 2]. Iodine from wet and dry deposition is accumulated i
 n soils\, transported by surface waters\, infiltrates groundwater\, and ma
 kes its way through the biosphere. One of the goals of this project is to 
 investigate the inventories of 129I and 127I in the pedosphere in Germany.
  \nStable iodine is analysed by using inductivity coupled plasma mass spec
 trometry (ICP-MS). The 129I /127I ratio is determined by means of accelera
 tor mass spectrometry (AMS).\nSampling of different soil types at various 
 locations in Germany\, down to a depth of 50 cm\, is in progress. The samp
 les are taken from 0-5 cm\, 5-10 cm\, 10-20 cm\, 20-30 cm\, and 30-50 cm\,
  resp. \nThe 129I inventories of the first soils analysed range from 120 m
 Bq m-2 to 470 mBq m-2 (depth: 50 cm)\, with the higher values being found 
 in the northern and western parts of Germany. The profiles show a characte
 ristic distribution of the 129I /127I ratios\, with the highest values in 
 the organic rich topsoil layer and a distinctive decrease of the values wi
 th increasing depth. This indicates that anthropogenic 129I is strongly as
 sociated to soil organic matter\, and is released again in a very slow pro
 cess.\n\n[1] M.J.M. Wagner\, B. Dittrich-Hannen\, H.-A. Synal\, M. Suter\,
  U. Schotterer (1996)\, Nucl. Instr. Meth. Phys. Res. B 113\, 490-494.\n[2
 ] A. Aldahan\, V. Alfimov G. Possnert (2007)\, Appl. Geochem. 22\, 606–6
 18.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=182&sessionI
 d=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=182&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Validation of the method for Ni determination in NPP evaporator co
 ncentrates
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-183@cern.ch
DESCRIPTION:Speakers: Dr. SULAKOVA\, Jana (CTU Prague\, Czeck Republic)\nI
 n this work a procedure developed for direct determination of radionickel 
 in boric acid containg evaporator concentrate generated at VVER nuclear po
 wer plants has been validated for repeatability. For nickel separation\, t
 his method uses the composite material PAN-DMG (dimethylglyoxime incorpora
 ted in porous beads of polyacrylonitrile) to selectively bind 59+63Ni from
  the above mentioned concentrate. The PAN-DMG resin has been prepared by m
 ethods developed at our Department of nuclear chemistry at the Czech Techn
 ical University in Prague [1]. The method of 59\,63Ni separation on column
  filled with PAN-DMG from real boric acid concentrates\, that was validate
 d in this work\, has been developed in the thesis of Fišera [2]. In this 
 work the influence of different uncertainty sources on the repeatability o
 f this method has been studied. The repeatabilities of nickel separation\,
  sample preparation\, sample measurement\, was investigated in this work. 
 In addition\, influence of the type of scintillation cocktails used on the
  measurement was determined. The results obtained showed that as well as w
 hole method also the particular parts of the methods are repeatable.\n[1] 
 F. Sebesta\, Composite inorganic exchangers of metal ions based on polyacr
 ylonitrile and their use\, Thesis of habilitation (1997) FNSPE\, CTU in Pr
 ague\n[2] O. Fišera and F. Šebesta\, 59Ni and 63Ni separation from boric
  acid concentrates produced at NPP\, J.Radioanal. Nucl. Chem. (2010) 285: 
 519-523\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=183&sess
 ionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=183&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:TiO2 based absorber for uranium separation and 236U measurement wi
 th AMS
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-180@cern.ch
DESCRIPTION:Speakers: Dr. NEMEC\, Mojmir (Czech Technical University in Pr
 ague\, Brehova 7\, Prague 115 19\, Czech Republic)\nThe uranium separation
  from natural waters was studied at the Department of Nuclear Chemistry in
  late 80´s and early 90’s. TiO-PAN absorber (titanium dioxide embedded 
 in polyacrylonitrile) showed high sorption capacity for this element.	 \nT
 his composite absorber is planned to be used for uranium pre-concentration
  for measuring environmental 236U/U ratios by Accelerator Mass Spectrometr
 y (AMS). After the preliminary AMS results showing anthropogenic contamina
 tion in TiO-PAN absorber\, the preparation of titanium oxide was studied w
 ith a strong emphasis on elimination of this contamination. \nHence\, tita
 nium dioxide materials were prepared from an organic uranium-free compound
 . These samples were then characterized for their crystal structure\, thei
 r specific surface area\, and their sorption towards uranium. Detailed sor
 ption properties were determined also for TiO-PAN absorber including kinet
 ic experiments\, sorption isotherm\, and effect of several ions (Ca2+\; Mg
 2+\; Fe3+\; NO3-\; SO42-\; Cl-\; CO32-). In these experiments\, the uraniu
 m concentrations were measured by Time Resolved Laser Induces Fluorescence
  Spectrometry (TRLFS)\, which allows us to measure uranium concentrations 
 up to ppb level. A strong influence of Cl- ions present in the solutions w
 as seen\, thus the calibration of TRLFS has to be made in order to determi
 ne the correct uranium concentration.  \nPresently we are focusing on find
 ing a water source which is not anthropogenically contaminated in order to
  use this water for further experiments and on the following separation an
 d concentration steps for AMS sample preparation.\n\nhttp://indico.cern.ch
 /contributionDisplay.py?contribId=180&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=180&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Separation of radioiodine by dry distillation process from irradia
 ted elemental Te target
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-181@cern.ch
DESCRIPTION:Speakers: Dr. MISIAK\, Ryszard (The Henryk Niewodniczański In
 stitute of Nuclear Physics Polish Academy of Sciences\, Cracow\, Poland)\,
  Mr. BARTYZEL\, Mirosław (The Henryk Niewodniczański Institute of Nuclea
 r Physics Polish Academy of Sciences\, Cracow\, Poland)\, Mr. WĄS\, Bogda
 n (The Henryk Niewodniczański Institute of Nuclear Physics Polish Academy
  of Sciences\, Cracow\, Poland)\nAbstract – The yield of release of radi
 oiodine from pressed elemental tellurium target and both sublimation and e
 vaporation rate of target material were investigated under different exper
 imental conditions.\n\nKeywords – elemental tellurium target\, dry disti
 llation\n\nI. Introduction\n\nA separation of radioiodine by a dry distill
 ation from irradiated TeO2 target is widely used[1-6]. Until now\, one wor
 k on studies on the separation of radioiodine by dry distillation from irr
 adiated elemental tellurium target was published by Acerbi et. al.[7] in t
 he seventies. In recent years the separation of radioiodine by anion-excha
 nge and solvent extraction from metallic tellurium target was also investi
 gated[8]. In the present work the dry distillation method of radioiodine f
 rom irradiated elemental tellurium target was studied.\n\nII. Experimental
 \n\nThe thickness of pressed tellurium powder with a natural isotopic comp
 osition was about 320 mg/cm2. Some of the targets were initially heated at
  a temperature 713 K and pressure 0.7 Pa by 10 minutes before an irradiati
 on. The irradiation condition was 20 nA as proton of energy 60 MeV for 2-3
  h at the Cracow AIC-144 cyclotron. Target after irradiation was placed in
  a quartz tube of 10 mm diameter. Performed two series of experiments: und
 er reduced pressure – 0.7 Pa and at a flow of Ar - 15 cm3/min. The durat
 ion of each experiment was 40 minutes after reaching a given temperature.\
 n\nIII. Results and discussion\n\nThe yield of release of radioiodine from
  target matrix and evaporation rate of target material were investigated u
 nder reduced pressure – 0.7 Pa for temperatures from 713 K to 823 K. The
  yield of release of radioiodine was about 65% for 713 K and reached the v
 alue 95% for 823 K. The tellurium loss in the separation conditions was 4%
  for temperature 713 K and increasing to 44% for 823 K. In the second seri
 es of experiments initially heated targets and Ar gas flux of 15 cm3/min w
 ere used for temperatures lower then the melting point – 723 K of tellur
 ium from 623 K to 713 K. A low yield of separation radioiodine was observe
 d in the temperature range 623 K to 673 K. With the increase of process te
 mperature to 713 K a significant increase of yield of dry distillation of 
 iodine took place and reached the value about 65%. The tellurium losses in
  this temperature were from 3 to 4%. Comparing the obtained results of yie
 ld of release of radioiodine for targets with and without initially heatin
 g showed that the yield was higher by 12% at 698 K and about 17% at 713 K 
 for targets without heating. There was no significant differences between 
 the target material losses for a given temperatures. The sublimated tellur
 ium condensed from 656 K to 575 K but the adsorption zone of radioiodine s
 tarting from 575 K to 320 K at the flow conditions. Due to overlapping the
  peaks the loss of radioiodine was 1\,5%.\n\nIV. Conclusion\n\nThe studies
  allowed to obtain the following conditions for the separation process: yi
 eld of release of radioiodine 85% (target without initially heating) and 6
 5% (target with initially heating) at temperature 713 K. It follows that t
 o achieve 85% efficiency of release will be required to reestablish the or
 iginal properties of the tellurium powder. The sublimation of tellurium wa
 s 3-4% from initial mass.  In comparison with TeO2 target the yield of sep
 aration of radioiodine is lower then 14% (for the 40 minutes experiment). 
 Taking into account the adsorption temperature of radioiodine it is possib
 le to transport radioiodine to attached trapping device by heating the par
 t of quartz tube beetwen end of furnace and attached trapping device at te
 mperature above 385 K. Based on the results further tests are planned.\n\n
 Acknowledgement: The work was done within framework of Polish Governmental
  Strategic Project: Supporting technologies for the development of safe nu
 clear power\, Action 4: Development of techniques and technologies support
 ing management of spent nuclear fuel and radioactive waste (No SP/J/4/1433
 21/11)\n\n1. R. Van Den Bosch\, J.J.M. De Goeij\, J.A. Van Der Heide\, J.F
 .W. Tertoolen\, H.M.J. Theelen\, C. Zegers\, „A new approach to target c
 hemistry fort he iodine-123 production via the 124Te(p\,2n) reaction.”\,
  International Journal of Applied Radiation and Isotopes 28 (1977) 255\n2.
  F. Oberdorfer\, F. Helus\, W. Maier-Borst\, “Experiences in the routine
  production of 123I via the 124Te(p\,2n)123I reaction with a low energy cy
 clotron”\, Journal of Radioanalytical Chemistry 65 (1981) 51\n3. E. J. K
 nust\, K. Dutschka\, R. Weinreich\, “Preparation of 124I solutions after
  thermodistillation of irradiated 124TeO2 targets”\, Applied Radiation a
 nd Isotopes 52 (2000) 181\n4. Matthias Glaser\, D.B. Mackay\, A.S.O. Ranic
 ar\, S.L. Waters\, F. Brady\, and S.K. Luthra\, “Improved targetry and p
 roduction of iodine-124 for PET studies.”\, Radiochimica Acta 92 (2004) 
 951\n5. Jonathon A. Nye\, Miguel A. Avila-Rodriguez\, and Robert J. Nickle
 s\, “Production of [124I]-iodine on an 11 MeV cyclotron.”\, Radiochimi
 ca Acta 94 (2006) 213\n6. Kotaro Nagatsu\, Masami Fukada\, Katsuyuki Mineg
 ishi\, Hisashi Suzuki\, Toshimitsu Fukumura\, Hiromichi Yamazaki\, Kazutos
 hi Suzuki\, “Fully automated production of iodine-124 using a vertical b
 eam.”\, Applied Radiation and Isotopes 69 (2011) 146\n7. E. Acerbi\, C. 
 Birattari\, M. Castiglioni\, F. Resmini\, “123I production at the Milan 
 AVF Cyclotron”\, Journal of Radioanalytical Chemistry 34 (1976) 87\n8. K
 . M. El-Azony and S. M. Qaim\, „ Anion-exchange and solvent extraction s
 tudies on the separation of radioiodine with particular reference to the p
 roduction of 123I via proton irradiation of 123Te metal target.”\, Journ
 al of Radioanalytical and Nuclear Chemistry 275 (2008) 275\n\nhttp://indic
 o.cern.ch/contributionDisplay.py?contribId=181&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=181&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Mineral Elements Determination in Medicinal Plants
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-186@cern.ch
DESCRIPTION:Speakers: SILVA\, Paulo (Instituto de Pesquisas Energéticas e
  Nucleares\, Brasil)\nThe demand for herbal medicines is growing worldwide
 . According to data from the World Health Organization\, approximately 80%
  of world population has resorted to the benefits of certain herbs with th
 erapeutic action popularly recognized. The determination of major\, minor 
 and trace elements and the research of metabolic processes and their impac
 ts on human health is of great importance due to the growth of environment
 al pollution that directly affects the plants and therefore the phytoterap
 ics. Therefore\, the objective of this paper was to determine the content 
 of inorganic constituents in herbal medicine: moisture\, inorganic ash\, t
 otal ash\, and the elements As\, Ba\, Br\, Ca\, Cs\, Co\, Cr\, Fe\, Hf\, K
 \, Na\, Rb\, Sb\, Sc\, Se\, Ta\, Th\, U\, Zn and Zr by neutron activation 
 analysis in medicinal plants in order to verify the quality of products as
  well as their correlation with reference standards.\nThis study presents 
 the results obtained for 59 medicinal plants commonly used in Brazil. Impu
 rities were found in levels up 50% of the sample. The moisture levels vari
 ed from 0\,1 to 12%. The concentrations obtained varied in a wide range fo
 r almost all the determined elements and the variation coefficient ranged 
 from 50 to 245%. Good agreement was found between the results obtained in 
 this work and the levels of trace elements reported in literature although
  high values for elements such as Ca\, Ba\, Cr\, Fe and Zn were found in s
 ome samples.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=186
 &sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=186&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Neptunium Redox Chemistry in Irradiated HNO3 Solutions
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-187@cern.ch
DESCRIPTION:Speakers: Dr. PAULENOVA\, Alena (Oregon State University\, USA
 )\nThe reliable separation methods for neptunium assume the ability to mai
 ntain a preferred oxidation state. However\, regardless of its initial red
 ox speciation\, a series of reactions occurs in nitric acid to create a mi
 xture of oxidation states including Np(V)\, Np(VI) and sometimes Np(IV).  
 Additionally\, the irradiated solutions such as dissolved nuclear fuel con
 tain both transient and long-lived radiolysis products which may be strong
 ly oxidizing or reducing. Thus\, irradiation may be expected to impact the
  chemical equilibrium and distributions of neptunium of various oxidation 
 states.\n Among the transient products of the irradiation of aqueous nitri
 c acid are the reducing •H atom and solvated electron and the oxidizing 
 •OH radical from water radiolysis\, and the oxidizing •NO3 and •NO2 
 radicals from nitric acid radiolysis. Longer-lived radiolysis products inc
 lude hydrogen peroxide from water radiolysis and nitrous acid from nitric 
 acid radiolysis. While it has been known that HNO2 acts as a reducing agen
 t toward Np(VI)\; the effects of the oxidizing transient species have been
  much less studied.\nSolutions of neptunium in nitric acid irradiated with
  Co-60 gamma-rays were analyzed by UV/Vis spectroscopy on radiolytically-i
 nduced changes in neptunium valences\, as well as the nitrous acid concent
 ration. It was found that at low absorbed doses\, the oxidizing radicals o
 xidized Np(V) to Np(VI). However\, as the irradiation proceeded the concen
 tration of nitrous acid became sufficient to reduce Np(VI) to Np(V)\, and 
 then continued irradiation favored this reduction until an equilibrium was
  achieved in balance with the oxidation of Np(V) by nitric acid itself. Th
 e starting concentrations of the two neptunium valences did not affect the
  final equilibrium concentrations of Np(V) and Np(VI).\n\nhttp://indico.ce
 rn.ch/contributionDisplay.py?contribId=187&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=187&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Mineral Nutrients in Brazilian Commercial Dog Foods
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-184@cern.ch
DESCRIPTION:Speakers: Ms. ELIAS\, Camila (CENA/USP\, Brasil)\nMineral nutr
 ients are essential chemical elements for a normal development of dogs. Th
 ere are two groups of mineral nutrients required by dogs\, macro minerals 
 (Ca\, P\, K\, Na\, Cl and Mg) and trace minerals (Fe\, Cu\, Zn\, Mn\, Se\,
  I).  The body cannot synthesize any of them\, thus dietary supplementatio
 n in proper quantity is crucial. Oversupplementation of one element may re
 sult in the deficiency of another\, due to the interaction among minerals 
 in the body. Either high or low level of a particular mineral in the diet 
 can be harmful to dog's health\, especially for growing puppies. Commercia
 l dog foods must have balanced levels of mineral nutrients\, which should 
 follow regulations as that of the Association of American Feed Control Off
 icials (AAFCO). In this context\, a comprehensive sampling of dry dog food
  for puppies and adults of various brands was performed in the local marke
 t of Piracicaba city\, Brazil\, for evaluating the adequacy of mineral nut
 rients. Instrumental neutron activation analysis (INAA) was chosen to asse
 ss the chemical composition of the dog food\, using two irradiations for d
 etermining both short and long-lived radionuclides. The moisture content o
 f samples ranged from 5% to 12% in compliance with the values required by 
 the Brazilian legislation for dry dog food. INAA was a suitable analytical
  tool for characterizing the profile of mineral nutrients in dog food\, al
 lowing the determination of Ca\, P\, K\, Na\, Cl\, Mg\, Fe\, Cu\, Mn\, Zn\
 , I and Se. In general\, all concentrations of mineral nutrients were with
 in the permissible limits established by AAFCO for growing puppies and adu
 lts\, with some slight deviations. Therefore\, one can consider the Brazil
 ian commercial dog foods as having good quality in terms of mineral nutrie
 nts.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=184&session
 Id=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=184&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Novel mesoporous materials for actinide and lant
 hanide separation
DTSTART;VALUE=DATE-TIME:20120919T143000Z
DTEND;VALUE=DATE-TIME:20120919T145000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-185@cern.ch
DESCRIPTION:Speakers: Prof. NITSCHE\, Heino (University of California\, Be
 rkeley\, Department of Chemistry\, USA)\nWe have undertaken the design\, s
 ynthesis\, and testing of reusable mesoporous materials for actinide and l
 anthanide separation\, sequestration\, and sensing.  An experimental-compu
 tational collaboration has yielded several materials with a high binding c
 apacity for 239Pu: functionalized mesoporous silica\, mesoporous carbon\, 
 and ferrihydrite.  Advances have been made with all three types of materia
 ls.  The affinity for target actinides of several ligands grafted to mesop
 orous silica\, as well as their binding geometry\, has been predicted by a
 b initio relativistic density functional theory (DFT) geometry optimizatio
 n calculations\, and compared to experimental batch sorption and X-ray abs
 orption spectroscopy (XAS) measurements.  Additionally\, these batch studi
 es have established the ability to reuse the materials as high-capacity so
 rbents.  Ordered mesoporous carbon (OMC) has proven far superior to activa
 ted carbon in terms of Pu(VI) capacity and sorption kinetics.  Batch and X
 AS studies of mesoporous and nanoparticulate ferrihydrite interactions wit
 h Pu(VI) have revealed interesting light-induced redox chemistry at the ir
 on-oxide surface that may yield separation capabilities. Alternative forms
  of these materials\, such as monoliths and thin films\, are being explore
 d but functionalization is a major challenge. We are expanding our studies
  to different actinide and lanthanides  ions and examine the effects of th
 e presence of competing ions\, as well as systematic ligand variation.  We
  are exploring OMC-based electrodes offer a promising route for electroche
 mical separation and sensing of actinides and lanthanides.\n\nhttp://indic
 o.cern.ch/contributionDisplay.py?contribId=185&sessionId=25&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=185&sessionId=2
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:The air-water partitioning of radon in groundwater contaminated by
  BTEX
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-189@cern.ch
DESCRIPTION:Speakers: Dr. LEE\, Kil Yong (Korea Institute of Geoscience an
 d Mineral Resources\, Korea)\nIt is well known that organic solvent\, such
  as benzene and toluene\, has the highest level of solubility for radon\, 
 being approximately 50 times higher than the solubility of radon in water 
 at the same environmental conditions such as temperature and pressure. The
  inhomogeneous distribution of radon between water and organic compounds a
 llows for utilizing naturally occurring radon as aqueous tracer for the as
 sessment of residual organic contamination of aquifers. In the present wor
 k\, the air-water partitioning coefficient of radon in water contaminated 
 by organic compounds were measured by a modified equilibrium partitioning 
 in closed system (MEPICS) technique using a liquid scintillation counter (
 LSC). The organic compounds were benzene\, toluene\, ethyl benzene and xyl
 ene (BTEX). A radioactive standard solution (SRM4967\, NIST) of radium (Ra
 -226) was used as a radon source of groundwater. The MEPICS method was app
 lied to measure the partitioning coefficient of radon in pure water and an
  artificial water containing 30μg/L BTEX at 25 °C.\n\nhttp://indico.cern
 .ch/contributionDisplay.py?contribId=189&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=189&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Development of a liquid scintillation detection system for aqueous
  chemistry of seaborgium
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-202@cern.ch
DESCRIPTION:Speakers: Mrs. KOMORI\, Yukiko (Osaka University\, Japan)\nAs 
 relativistic effects on the valence electrons become large in heavy elemen
 ts\, it is interesting to elucidate chemical properties of the transactini
 de elements. In these chemical experiments\, an automated and rapid chemis
 try apparatus coupled to an α-particle detection system is required. In t
 he present study\, we have developed an on-line liquid scintillation detec
 tion system to measure solution samples eluted from the chemistry apparatu
 s for aqueous chemistry of element 106\, seaborgium (Sg).  \nWe fabricated
  a liquid scintillation detector which consists of a photomultiplier tube 
 and a glass cell set in a semispherical reflector. The nuclide 265Sg decay
 s by α-particle emission and the daughter nuclide\, 261Rf\, decays by α-
 particle emission or spontaneous fission (SF). Therefore\, to detect both 
 α particles and SF fragments is required for the determination of Sg. Ene
 rgy resolution and detection efficiency in α-particle detection were meas
 ured using the nuclides 226Ra and 241Am. Response to the SF events was inv
 estigated using the nuclide 252Cf. Procedures in on-line measurements are 
 as follows. An emulsifier scintillator was first introduced into the cell.
  The aqueous solution sample from the chemistry apparatus was then injecte
 d to the cell. During the injection\, the scintillator and the solution sa
 mple were mixed with an electromagnetic stirrer. Measurement was started a
 fter the mixture became homogeneous in the cell. The above procedures were
  automatically and repeatedly performed.\nThe present detection system was
  applied to the on-line measurement of 213Fr (T1/2 = 34.6 s) produced in t
 he 209Bi(16O\, 4n)221Pa reaction using the AVF cyclotron at RCNP. The reac
 tion products were transported to the chemistry laboratory by a He/KCl gas
 -jet system and were collected on the collection site of the ion-exchange 
 apparatus\, ARCA\, for 1 min. The collected products were then dissolved i
 n 200 μL of 0.1 M HNO3/5 × 10-3 M HF solution for 12 s. The eluent was t
 ransferred to the cell and mixed with 4 mL of the scintillator. Start of m
 easurement of the products was approximately 15 s after the end of collect
 ion.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=202&session
 Id=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=202&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Development of diet-induced obesity in the rat\, followed by radio
 analytical methods
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-99@cern.ch
DESCRIPTION:Speakers: Dr. PAVELKA\, Stanislav (Institute of Physiology\, A
 SCR\, Prague/Masaryk University\, Brno)\nPavelka S.1\,2\, Macek Jílková 
 Z.3 and Kopecký J.3\n\n1Department of Radiometry\, Institute of Physiolog
 y\, v.v.i.\, Academy of Sciences of the Czech Republic\, Prague\; 2Institu
 te of Biochemistry\, Masaryk University\, Brno\; and 3Department of Adipos
 e Tissue Biology\, Institute of Physiology\, v.v.i.\, ASCR\, Prague\, Czec
 h Republic\n\n\nHigh-fat-feeding induction and development of obesity was 
 followed in male C57BL/6J mice maintained on a special high-fat (HF) diet\
 , in comparison with the same animals maintained on a standard low-fat (LF
 ) diet. In parallel to several morphological parameters\, changes in the t
 hyroid status of the animals were followed. Serum total thyroxine (T4) and
  3\,5\,3’-triiodothyronine (T3) concentrations were determined using rad
 ioimmunoanalytical kits. Moreover\, with the aid of our newly developed ra
 diometric enzyme assay\, we measured changes in the enzyme activity of typ
 e 3 iodothyronine deiodinase (D3) in several depots of murine white adipos
 e tissue (WAT). D3 is the key enzyme in the metabolism of thyroid hormones
 \, converting biologically most active T3 and prohormone T4 into inactive 
 metabolites (3\,3’-diiodothyronine\, T2 and 3\,3‘\,5‘-triiodothyroni
 ne\, reverse T3\, respectively). HF-diet feeding resulted in an increased 
 size of adipocytes and in a significantly higher weight of both epididymal
 -visceral and dorsolumbar-subcutaneous fat depots. Total T4 and total T3 p
 lasma levels were significantly elevated in mice fed HF-diet\, in comparis
 on with mice maintained on LF-diet. Development of HF-diet-induced obesity
  in the mice was associated with an enhancement of D3 activity in WAT. Aft
 er maintaining the mice on      HF-diet for two weeks\, the D3 activity wa
 s significantly increased in their subcutaneous fat (142 ± 20 vs. 85 ± 1
 2 fmol T2/h/mg protein) but not so much in epididymal fat. In conclusion\,
  HF-diet-induced obesity in mice was associated with proliferation and dif
 ferentiation of WAT and stimulation of thyroid hormones metabolism in WAT.
  Support from the Academy of Sciences of the Czech Republic (Project No. A
 V0Z50110509) and from the Czech Science Foundation (GACR Grant No. 304/08/
 0256) is acknowledged.\n\nhttp://indico.cern.ch/contributionDisplay.py?con
 tribId=99&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=99&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Radiometric quantification of type 1 iodothyronine 5'-deiodinase a
 ctivity in human white adipose tissue
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-98@cern.ch
DESCRIPTION:Speakers: Dr. PAVELKA\, Stanislav (Institute of Physiology\, A
 SCR\, Prague/Masaryk University\, Brno)\nPavelka S.1\,2 \n\n1Department of
  Radiometry\, Institute of Physiology\, v.v.i.\, Academy of Sciences of th
 e Czech Republic\, Prague and  2Institute of Biochemistry\, Masaryk Univer
 sity\, Brno\, Czech Republic\n\nWhite adipose tissue (WAT) represents an i
 mportant target for thyroid hormones (TH)\, which are known to modulate ad
 ipose tissue metabolism and differentiation of adipocytes. However\, relat
 ively little is known about TH metabolism in WAT. Recently\, we determined
  higher activities of the key enzyme of TH metabolism\, type 1 iodothyroni
 ne 5’-deiodinase (D1)\, in obese compared to lean control mice. Moreover
 \, D1 activity in murine WAT could be stimulated by leptin\, a major adipo
 kine secreted in enhanced rate from hypertrophic adipose tissue. Based on 
 these results\, we aimed in the present study to measure activities of the
  three known iodothyronine deiodinases (IDs) in WAT of humans\, and to cha
 racterize their possible association with obesity. Omental (OM) and subcut
 aneous (SC) adipose tissue samples were obtained during elective surgical 
 procedures from a cohort of 70 human subjects with a body mass index (BMI)
  between 20 and 68 kg/m2. In a randomly selected subpopulation of 19 indiv
 iduals\, IDs activities of types 1 (D1)\, 2 (D2) and 3 (D3) were estimated
  in both OM and SC fat depots. IDs activities were measured in sub-mitocho
 ndrial supernatant fractions prepared from frozen WAT samples (10-40 g 
 protein in a final volume of 40 l) using our recently elaborated radiom
 etric enzyme assays. Specific D2 and D3 enzyme activities were close to th
 e detection limits and there were no apparent differences in these activit
 ies between obese and non-obese subjects. On the contrary\, activity of D1
  could be quantified and it was significantly higher in both OM (ca. four-
 fold\, P = 0.010) and SC (ca. eight-fold\, P = 0.004) fat of obese when co
 mpared with non-obese individuals. Indeed\, D1 activity correlated with BM
 I in both OM and SC fat depots. In conclusion\, we have demonstrated for t
 he first time in humans that (i) activities of enzymes involved in TH meta
 bolism in human WAT differed in subjects according to the degree of adipos
 ity\; and that (ii) D1 was increased in hypertrophic adipose tissue (in ob
 ese subjects). Support from the Academy of Sciences of the Czech Republic 
 (Project No. AV0Z50110509) and from the Czech Science Foundation (GACR Gra
 nt No. 304/08/0256) is acknowledged.\n\nhttp://indico.cern.ch/contribution
 Display.py?contribId=98&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=98&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:A preliminary study of prompt gamma-ray activation analysis using 
 pulsed neutron at J-PARC / ANNRI
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-168@cern.ch
DESCRIPTION:Speakers: Dr. TOH\, Yosuke (Japan Atomic Energy Agency\, Japan
 )\nThe Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) ha
 s been constructed at the beamline No. 04 at the Material and Life Science
  Experimental Facility (MLF) of the Japan Proton Accelerator Research Comp
 lex (J-PARC). ANNRI has been used for the measurement of nuclear cross-sec
 tion data\, nuclear astrophysics and prompt gamma-ray analysis (PGA). MLF 
 is a very intensive pulsed neutron facility\, and expected to reach 1 MW p
 roton beam power in the near future. The germanium detector-array\, which 
 consists of two cluster-Ge detectors\, eight coaxial-Ge detectors and BGO 
 Compton suppression detectors\, was installed at the flight length of 21.5
 m in ANNRI. It is designed to provide high gamma ray energy resolution and
  high detection efficiency. The time resolution of Ge detector is poor but
  this is not a disadvantage because of the proton beam pulse width of 0.1 
 micro sec. We have developed a time-of-flight prompt gamma-ray analysis co
 mbined with gamma-ray coincidence technique. Preliminary experiments of BC
 R CRM 680 and 681 (polyethylene reference material) etc. were made in ANNR
 I. The power of the proton beam was approximately 200 kW and the repetitio
 n of the neutron beam was 25 Hz. In this study\, the background spectra\, 
 the data acquisition dead time and the effect of the self-shield of neutro
 n flux\, which depend on the neutron energy\, have been measured and evalu
 ated. These are compared with the results of the experiments of multiple p
 rompt gamma-ray analysis at Japan Research Reactor-3\, and the similarity 
 and difference are discussed.\nThis study was supported in part by JSPS KA
 KENHI Grant Number (22750077).\n\nhttp://indico.cern.ch/contributionDispla
 y.py?contribId=168&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=168&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Vacuum thermochromatography - prospective method
  for heaviest element studies
DTSTART;VALUE=DATE-TIME:20120918T073000Z
DTEND;VALUE=DATE-TIME:20120918T075000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-169@cern.ch
DESCRIPTION:Speakers: Prof. ZVARA\, Ivo (JINR Dubna\, Russia)\nThe title t
 echnique for separating species with dissimilar adsorbability uses deeply 
 evacuated columns with imposed negative longitudinal temperature gradient.
  Then the molecular flow\, though convectionless\, produces deposits peaki
 ng in individual temperature ranges. This fundamental mechanism - random w
 alks from wall to wall - calls for rigorous Monte Carlo (MC) simulations\,
  which require a minimum of assumptions\, are very versatile in accounting
  for numerous parameters and conditions of real experiments\, but are slow
 . Diffusional approximation of random walks with solution to the appropria
 te differential equation gives excellent agreement with MC. The calculatio
 ns are faster for some basic conditions\, but the versatility is much poor
 er. Meanwhile\, the structure of the solution suggests a way to a semi the
 oretical explicit formula for the peak. The one presented here is negligib
 ly inaccurate\, reasonably versatile\, and unmatched in the speed of the n
 ecessary calculations. It greatly enables evaluation of the experiments wi
 th a few radioactive atoms or labeled molecules\, which is the case in tod
 ay chemical studies of the superheavy elements. This is demonstrated by si
 mulating experimental data of this kind for certain desorption energy and 
 then\, backward\, evaluating the confidence intervals for the "experimenta
 l" value of the energy. The Bayesian approach is used\; several caveats on
  hasty conclusions at poor statistics are emphasized. Some considerations 
 about the real experiments are presented.\n\nhttp://indico.cern.ch/contrib
 utionDisplay.py?contribId=169&sessionId=20&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=169&sessionId=2
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Trace Element Analysis with high sensitivity spe
 ctrometry.
DTSTART;VALUE=DATE-TIME:20120921T072000Z
DTEND;VALUE=DATE-TIME:20120921T074000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-229@cern.ch
DESCRIPTION:Speakers: Dr. PREVITALI\, Ezio (Istituto Nazionale di Fisica N
 ucleare\, Sez. Milano Bicocca\, Italy)\nIn high sensitive experiments for 
 rare events physics searches\, the determination of contaminants is one of
  the most critical issue. Radioactive contamination in constructing materi
 als can mimic the tiny signal of the studied events and this reduces the g
 lobal experimental sensitivities. To fulfill the requests of experiments l
 ike double beta decay or dark matter searches\, sensitivities in the scale
  of microBq/kg for 238U and 232Th chains are actually needed: such measure
 ment capabilities are normally not accessible from standard instrumentatio
 ns.\nMany spectroscopic techniques were developed in order to reach the re
 quested sensitivities and to guaranty the correct selection of the detecto
 rs materials. In this way also the construction of the spectrometers need 
 particular cares and specific approaches.\nActually HPGe spectrometers spe
 cifically constructed reach very high capabilities in the detection of ver
 y low radioactive background in ultra pure materials. These detectors were
  realized using the same approach as that adopted for low background exper
 iments that give us the methodological approach to increase their measurem
 ent sensitivities.\nMethods\, instrumentations and specific data analysis 
 developed for very high sensitive measurements will be presented. Applicat
 ions of these high sensitivities techniques to other field of scientific r
 esearchers will be also discussed.\n\nhttp://indico.cern.ch/contributionDi
 splay.py?contribId=229&sessionId=30&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=229&sessionId=3
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Neutron activation analysis: a consolidated anal
 ytical tool in the sugarcane agroindustry
DTSTART;VALUE=DATE-TIME:20120920T062000Z
DTEND;VALUE=DATE-TIME:20120920T064000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-228@cern.ch
DESCRIPTION:Speakers: Prof. DE NADAI FERNANDES\, Elisabete (Nuclear Energy
  Center for Agriculture\, University of Sao Paulo\, Brasil)\nCurrently\, B
 razil has become a leader in development of science and technology for the
  agribusiness sector of sugarcane. The country has maintained a tradition 
 of decades as the world's largest producer of sugarcane preferentially ori
 ented to the production of sugar and ethanol. In addition\, bioelectricity
  generated by the burning of bagasse is employed to power mills with elect
 ric power remaining being sold to make a clean process\, which avoids the 
 use of fossil fuels. More recently\, innovative products derived from suga
 rcane as biodegradable plastics and essential amino acids have emerged and
  gained competitiveness in the market for economic and environmental reaso
 ns. Ethanol from sugar cane has been the most successful biofuel in the wo
 rld\, evidencing the enormous contribution of sugarcane to sustainability 
 in the production of clean fuels and reduction of greenhouse gas emissions
 . Nevertheless\, there is potential to further increase the competitivenes
 s of products derived from sugarcane\, with more sophisticated management 
 of the production process\, including quality control\, optimization of pa
 rtnerships between growers and industry\, increased efficiency in the ferm
 entation process\, among others. To comply with the demand for one billion
  tons of sugarcane in 2020\, new varieties with higher productivity have b
 een developed\, including genetic modified ones. For evaluating the geneti
 c improvement\, specific certified reference materials are being developed
  at CENA/USP. Neutron activation analysis has been successfully applied si
 nce 1986 to the various segments of the sugarcane productive chain\, there
 by contributing to the efficacy of the system. By assessing the amount of 
 soil adhered to sugarcane stalks transported to the industry\, tracking th
 ose mineral impurities in the entire production process\, comprising washi
 ng efficiency\, bagasse\, juice\, sugar and yeasts\, it was possible to ac
 curately measure the influence of soil type\, moisture content\, soil prep
 aration techniques and the overall impact on the sugarcane payment system.
 \n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=228&sessionId=2
 7&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=228&sessionId=2
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:A novel path in partitioning: Water-soluble BTP ligands for the in
 novative SANEX process
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-91@cern.ch
DESCRIPTION:Speakers: Prof. PANAK\, Petra (University of Heidelberg\, Germ
 any)\nWith regard to an efficient partitioning process the separation of t
 he trivalent minor actinides from the chemically similar fission lanthanid
 es is one of the key issues. This separation process requires highly effec
 tive extracting agents. Alkylated bis(1\,2\,4-triazin-3-yl)pyridines (BTP)
  and alkylated bis([1\,2\,4]triazin-3-yl)-[2\,2’]bipyridines (BTBP) are 
 among the most promising SANEX extracting agents\, selectively extracting 
 trivalent actinides from nitric acid solutions. Based on the conventional 
 SANEX process an innovative SANEX (i-SANEX) process has been developed\, c
 ombining the SANEX with the previous DIAMEX step. Hydrophilic aq-BTP is us
 ed as aqueous complexing agent for selective back extraction of actinides 
 from organic phases loaded with trivalent actinides and lanthanides. Our s
 tudies focus on the complexation of trivalent actinides and lanthanides wi
 th aq-BTP (a) to gain fundamental knowledge on the unique properties of BT
 P\, (b) to compare BTP with aq-BTP\, and (c) to determine complex formatio
 n constants for trivalent actinides and lanthanides required for future pr
 ocess development. In the present work complexation studies are performed 
 with Cm(III)/Eu(III) using time-resolved laser fluorescence spectroscopy (
 TRLFS). With increasing ligand concentration the following complexes are i
 dentified and spectroscopically characterised: [M(aq-BTP)]\, [M(aq-BTP)2]\
 , and [M(aq-BTP)3] (M: Cm(III)\, Eu(III)). From our spectroscopic results 
 the stability constants and thermodynamic data of the stepwise complex for
 mation are derived. A comparison of the log K values of the [M(aq-BTP)3]-c
 omplexes (M = Eu(III)\, Cm(III)) shows a significantly higher stability co
 nstant for trivalent actinides\, which is in perfect agreement with the se
 lectivity observed in liquid-liquid extraction tests.\n\nhttp://indico.cer
 n.ch/contributionDisplay.py?contribId=91&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=91&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Study of neptunium sorption on clay and clay min
 erals using X-ray absorption spectroscopy
DTSTART;VALUE=DATE-TIME:20120921T070000Z
DTEND;VALUE=DATE-TIME:20120921T072000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-90@cern.ch
DESCRIPTION:Speakers: Prof. REICH\, Tobias (Johannes Gutenberg-Universitä
 t Mainz\, Germany)\nIn several European countries argillaceous rocks have 
 been considered as potential host rock for the construction of radioactive
  waste disposal repositories. Among potential migration paths\, sorption a
 nd diffusion of radionuclides are the most important processes for the mig
 ration of these elements beyond the engineered barriers of the repository.
 \nWe have investigated the sorption of neptunium(V)\, the most mobile and 
 soluble species of Np\, on clay minerals [1] as well as on natural Opalinu
 s clay (Mont Terri\, Switzerland) [2]. The interactions between Np(V) and 
 the clay and clay minerals have been studied by batch experiments as a fun
 ction of several chemical parameters and by synchrotron-based techniques.\
 nBefore presenting the results for Opalinus clay\, the most important find
 ings of batch and EXAFS studies of Np(V) sorption on pure clay mineral pha
 ses will be briefly reviewed. Since Opalinus clay has a heterogeneous comp
 osition\, the sorption of Np(V) has been studied by microfocused synchrotr
 on X-ray fluorescence (µ-XRF) mapping\, microfocused-XANES spectroscopy (
 µ-XANES) and microfocused X-ray diffraction (µ-XRD) at the Swiss Light S
 ource. By combining these synchrotron-based techniques\, the following res
 ults were obtained [3]: 1) Considerable amounts of Np(IV) were detected in
  areas that are enriched in Np\, even when the sorption experiments with N
 p(V) were conducted in air. 2) Under anaerobic conditions\, a correlation 
 between Np and Fe was observed in the µ-XRF maps\, indicating that the re
 duction of Np(V) is caused by an iron(II)-containing mineral that could be
  identified as pyrite by µ-XRD. The reduction of Np(V) to the less mobile
  Np(IV) is an important process that increases the sorption of this long-l
 ived radiotoxic element and retards its migration through the clay.\n\nRef
 erences\n[1] S. Amayri et al.\, Radiochim. Acta 99 (2011) 349\n[2] D.R. Fr
 öhlich et al.\, Radiochim. Acta 99 (2011) 71\n[3] D.R Fröhlich et al.\, 
 Anal. Bioanal. Chem. (submitted)\n\nhttp://indico.cern.ch/contributionDisp
 lay.py?contribId=90&sessionId=30&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=90&sessionId=30
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Non-destructive and quantitative multi-elemental analysis by muoni
 c X-ray spectroscopy for archeological bronze samples
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-166@cern.ch
DESCRIPTION:Speakers: Dr. NINOMIYA\, Kazuhiko (Osaka University\, Japan)\n
 Quantitative elemental analysis is one of the most important themes in the
  field of natural science. For example\, in the field of archeology\, dete
 rmination of elemental composition provides useful information to understa
 nding the history and propagation of technology and culture. The archeolog
 ical samples are highly valuable and the surface of these samples is usual
 ly oxidized or coated. Therefore\, it is essential to get elemental compos
 ition deeply inside of the sample without destruction\, however\, such an 
 analysis method is very limited. \nIn this paper\, we report the developme
 nt of a non-destructive\, position-sensitive and quantitative multi-elemen
 tal analysis method for bulk samples by characteristic muonic X-ray measur
 ements. When a negative muon that is one of the elementally particles is s
 topped in material\, the muon is captured on a nucleus and muonic atom is 
 formed. A muonic atom is an atomic system that has one negatively charged 
 muon instead of an atomic electron. After formation of the muonic atom\, t
 he captured muon immediately de-excites to lower muon atomic levels throug
 h muon characteristic X-ray emissions. Because the mass of the muon is 207
  times larger than that of the electron\, characteristic muonic X-ray is m
 uch harder than electronic X-ray and muonic X-rays even from inside of a b
 ulk sample are detectable.\nIn this study\, we determined the elemental co
 mposition of old Japanese coins (tempo-tsuho) and old Chinese mirror (seiu
 n-kyo). Muon irradiation experiments were performed in J-PARC (Japan) and 
 Rutherford Appleton Laboratory (UK). Characteristic muonic X-rays were mea
 sured by high purity germanium detectors. We also performed muon irradiati
 on for standard bronze samples to determine relation between characteristi
 c muonic X-ray intensity and elemental composition. The details will be di
 scussed in our presentation.\n\nhttp://indico.cern.ch/contributionDisplay.
 py?contribId=166&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=166&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Application of microbeam synchrotron technique
 s to determine the distribution and speciation of plutonium after uptake b
 y Opalinus Clay
DTSTART;VALUE=DATE-TIME:20120921T112500Z
DTEND;VALUE=DATE-TIME:20120921T114000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-95@cern.ch
DESCRIPTION:Speakers: Dr. AMAYRI\, Samer (Johannes Gutenberg-Universität 
 Mainz\, Institute of Nuclear Chemistry\, 55099 Mainz\, Germany)\nThe synch
 rotron radiation based techniques X-ray fluorescence (XRF) and X-ray absor
 ption spectroscopy (XANES: X-ray absorption near edge structure) have been
  used to determine the distribution and the chemical speciation of plutoni
 um (Pu) after sorption and diffusion in Opalinus Clay (OPA\, Mont Terri\, 
 Switzerland). Thin sections of OPA were contacted with 20 µM Pu(VI)-242 i
 n OPA pore water (pH 7.6\, I=0.4 M) under aerobic conditions for at least 
 3 days. For comparison\, a OPA bore core in a diffusion cell was contacted
  with 20 µM Pu(VI)-242 under the same conditions for 4 weeks. The sorptio
 n and diffusion samples were investigated at the MicroXAS beamline at the 
 Swiss Light Source\, Paul Scherrer Institut\, Switzerland. µ-XRF mapping 
 has been used to determine the elemental distribution of Pu and other elem
 ents contained in OPA\, e.g.\, Fe and Ca. Regions of high Pu concentration
 s were subsequently investigated by µ-XANES to identify the oxidation sta
 te of sorbed Pu on the surface of OPA. Further\, µ-XRD (X-ray diffraction
 ) was employed to gain knowledge about reactive crystalline mineral phases
  in the vicinity of Pu enrichments. The results of Pu L3-edge µ-XANES spe
 ctra on Pu hot spots showed that Pu(IV) is the dominating species on OPA\,
  i.e.\, the highly soluble Pu(VI) was retained by OPA in the reduced and l
 ess mobile tetravalent oxidation state of Pu. µ-XRD results indicated tha
 t Pu is localized on or in the close vicinity of the Fe(II)-bearing minera
 l siderite and the clay mineral illite. Siderite is one of the redox-activ
 e mineral phases of OPA\, which determines the speciation on Pu after upta
 ke on OPA.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=95&se
 ssionId=31&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=95&sessionId=31
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Rapid Radiochemical Analysis of Radionuclides Di
 fficult to Measure in Environmental and Waste Samples
DTSTART;VALUE=DATE-TIME:20120918T103000Z
DTEND;VALUE=DATE-TIME:20120918T105000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-222@cern.ch
DESCRIPTION:Speakers: Dr. HOU\, Xiaolin (Center for Nuclear Technologies\,
  Technical University of Denmark\, Denmark)\nWith the increasing requireme
 nt on rapid reaction system fot nuclear emergency preparedness\, increasin
 g numbers of nuclear facilities being decommissioned\, as well as radioeco
 logical investigation\, a large number of environmental\, biological and w
 aste samples need to be rapid analyzed for various radionuclides. Except g
 amma emitting radionuclides\, other radionculides have to be first separat
 ed from the sample matrix and purified from the interferences before measu
 rement\, therefore defined as radionuclides difficult to measure. The trad
 itional analytical methods for these radionuclides normally take a few day
 s to weeks for one analysis\; this makes the emergency reaction impossible
  in one day\, and impossible to analyse a large number of sample from deco
 mmissioning work and radioecological investigation. In recent years\, cons
 iderable efforts have been focused on the development of automated and rap
 id analytical methods. In our laboratory\, automated analytical systems ha
 ve been established by exploiting flow/sequential injection approach\, usi
 ng chromatographic separation concept\, combined with rapid measurement of
  radionculides using ICP-MS. A number of analytical methods have been deve
 loped to determine 99Tc\, 237Np\, and isotopes of Pu and U in biological\,
  environmental and nuclear waste samples. This work aims to summarize thes
 e automated and rapid analytical methods for the determination of various 
 radionculides.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=2
 22&sessionId=21&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=222&sessionId=2
 1&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Quantification of iodothyronine deiodinases activities\, induced i
 n cultured astrocytes by purinergic agonists\, with the use of radiometric
  enzyme assays
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-97@cern.ch
DESCRIPTION:Speakers: Dr. PAVELKA\, Stanislav (Institute of Physiology\, A
 SCR\, Prague/Masaryk University\, Brno)\nPavelka S.1\,2\n\n1Department of 
 Radiometry\, Institute of Physiology\, v.v.i.\,  Academy of Sciences of th
 e Czech Republic\, Prague and 2Institute of Biochemistry\, Masaryk Univers
 ity\, Brno\, Czech Republic\n\nDescribed are details of our newly elaborat
 ed radiometric methods for extremely sensitive determination of enzyme act
 ivities of iodothyronine deiodinases (IDs) of types 1\, 2 and 3 in homogen
 ates of cultured mammalian cells. IDs catalyze selective 5’- (outer ring
 ) and 5- (inner ring) mono-deiodinations of iodothyronines and play crucia
 l roles in the bio-transformations of thyroid hormones. The novel radiomet
 ric assays for IDs were based on the use of appropriate high-specific-radi
 oactivity 125I-labeled iodothyronines as substrates\; TLC separation of ra
 dioactive products from the unconsumed substrates\; film-less autoradiogra
 phy of radiochromatograms using storage phosphor screens\; and quantificat
 ion of the separated compounds with a BAS-5000 (Fujifilm Life Science Co.)
  laser scanner. The applicability of our sophisticated radiometric methods
  was demonstrated by quantifying the alterations of IDs activities induced
  in cultured rat astroglial cells by a series of purinergic agonists (like
  ATP\, ADP\, AMP and adenosine)\, retinoic acid\, and their combination. T
 he newly developed radiometric assays proved to be very sensitive and rapi
 d and\, at the same time\, reliable and robust. Support from the Academy o
 f Sciences of the Czech Republic (Project No. AV0Z50110509) and from the C
 zech Science Foundation (GACR Grant No. 304/08/0256) is acknowledged.\n\nh
 ttp://indico.cern.ch/contributionDisplay.py?contribId=97&sessionId=26&conf
 Id=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=97&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Radiopharmacological studies of leptin and thy
 roid hormones relationship in white adipose tissue
DTSTART;VALUE=DATE-TIME:20120917T100000Z
DTEND;VALUE=DATE-TIME:20120917T101500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-96@cern.ch
DESCRIPTION:Speakers: Dr. PAVELKA\, Stanislav (Department of Radiometry\, 
 Institute of Physiology\, v.v.i.\,  Academy of Sciences of the Czech Repub
 lic\, Prague\; and Institute of Biochemistry\, Masaryk University\, Brno\,
  Czech Republic)\nPavelka S.1\,2\, Macek Jílková Z.3 and Kopecký J.3 \n
 \n1Department of Radiometry\, Institute of Physiology\, v.v.i.\, Academy o
 f Sciences of the Czech Republic\, Prague\; 2Institute of Biochemistry\, M
 asaryk University\, Brno\; and 3Department of Adipose Tissue Biology\, Ins
 titute of Physiology\, v.v.i.\,  ASCR\, Prague\, Czech Republic\n\nThe met
 abolism of thyroid hormones (TH) in white adipose tissue (WAT) is so far p
 oorly characterized. Therefore\, we followed changes in TH metabolism in m
 ice\, which were associated with the development of high-fat (HF) diet-ind
 uced obesity\, with the aid of several radioanalytical methods – radiome
 tric enzyme assays and radioimmunoanalysis (RIA)\, among others. Possible 
 changes in activities of the key enzymes of TH metabolism in murine WAT we
 re measured not only during obesogenic treatment of the mice but also in r
 esponse to caloric restriction or leptin administration. Adult male C57BL/
 6J mice were subjected to these three different treatment protocols. Subcu
 taneous and epididymal WAT and interscapular brown fat (BAT) depots were d
 issected and used for morphometric and enzymatic analyses. In addition\, b
 lood and samples of liver were also collected (and the latter used as cont
 rols for enzymatic determinations). Plasma levels of leptin\, as well as t
 otal and free thyroxine (T4) and triiodothyronine (T3) concentrations were
  determined using RIA kits. Enzyme activities of iodothyronine deiodinases
  of the types 1 (D1)\, 2 (D2) and 3 (D3) in the liver\, WAT and BAT were m
 easured with the aid of our newly developed radiometric enzyme assays. We 
 found that D1 enzyme activity in WAT was stimulated by a high-fat-diet fee
 ding\, which also increased plasma levels of leptin. However\, D1 or D2 ac
 tivities in BAT did not change. On the contrary\, caloric restriction decr
 eased D1 activity in WAT\, but not in the liver\, and reduced leptin level
 s. In return\, leptin injections increased D1 activity in WAT. In summary\
 , our results demonstrate\, for the first time\, changes in D1 activity in
  WAT under the conditions of changing adiposity\, and a stimulatory effect
  of leptin on D1 activity in WAT. Support from the Academy of Sciences of 
 the Czech Republic (Project No. AV0Z50110509) and from the Czech Science F
 oundation (GACR Grant No. 304/08/0256) is acknowledged.\n\nhttp://indico.c
 ern.ch/contributionDisplay.py?contribId=96&sessionId=15&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=96&sessionId=15
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Elemental analysis of rivers\, marshes and ground water in Thi Qar
  region\, Iraq
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-220@cern.ch
DESCRIPTION:Speakers: Dr. ALRAKABI\, Muhanad (Department of Physics\, Al M
 ustansiriya University\, Baghdad\, Iraq. Department of Physics\, Panjab Un
 iversity\, Chandigarh\, India)\nThe elemental analysis of the samples coll
 ected from marshes water\, river water and ground water in Thi Qar region 
 of Iraq are done using the Energy-dispersive X-ray fluorescence technique 
 (EDXRF). The water samples are collected from Al-Hammar marshes\, Central 
 marshes\, Tigris river and Euphrates river. The residues obtained after dr
 ying ground water are analyzed using the EDXRF spectrometer is consisting 
 of 42Mo-anode X-ray tube equipped with selective absorbers as an excitatio
 n source and a Si (Li) detector. The elements observed in various samples 
 are 20Ca\, 26Fe\, 29Cu\, 30Zn\, 33As\, 35Br\, 38Sr\, 82Pb and 92U. The pH 
 value of water samples from various locations of marshes\, rivers and grou
 nd waters are in general exceeding ~7.9 value\, which indicate the general
  alkaline nature of waters. The average value of leftover residue obtained
  after drying the water samples from Al-Hammar marshes is ~ 4.8 g/L\, whic
 h is about twice of that of Central marshes. The average value of total re
 sidue obtained after drying the water samples from Euphrates river is ~ 3 
 g/L\, which is about four times of that obtained from Tigris river water. 
 The Electrical Conductivity (EC) values measurements for these samples als
 o infer the similar conclusions. The 20Ca concentration in Tigris and Euph
 rates river waters is similar to that observed in Central marshes and is a
 bout half of the value in Al-Hammar marshes. The 20Ca concentration in Tig
 ris river water constitutes ~ 6 % of the leftover residue and that in Euph
 rates river water constitutes ~2.3 % of the total residue\, a value simila
 r to that observed in water from the marshes. The 38Sr concentrations in t
 he Tigris and Euphrates river waters are in the range 1390−1863¬ μg/L 
 and 2519−5691 ¬¬μg/L\, respectively. The 38Sr concentration in Euphra
 tes river is similar to that observed in the marshes water and that in Tig
 ris river is lower by a factor of 8. In Al-Hammar marshes\, 82Pb is observ
 ed with concentration ~ 60μg/L and the concentration of 34As is estimated
  to be in general below 5 μg/L. In Central marshes\, 28Ni and 29Cu are al
 so observed with average concentration of 40 and 28μg/L\, respectively. A
 verage value of concentration of the trace element 92U in both the marshes
  is below 10μg/L. The 35Br concentration in various samples collected fro
 m Al-Hammar marshes (average value = 1108 μg/L) are in general higher com
 pared to those from Central marshes (average value = 328 μg/L). The 35Br 
 concentration in various samples collected from Euphrates river (average v
 alue = 676 μg/L) are considerably higher compared to those from Tigris ri
 ver (average value = 47 μg/L). The presence of significantly high 35Br co
 ncentration in the river water is a matter of concern in case it is used f
 or drinking purpose after treatment. The normally present bromide anions c
 an generate bromate anions in the water purification based on ozonation or
  chlorination or ultra violet radiation. In case the Br concentration of w
 ater is very high\, it is likely that bromate ions will also be formed to 
 significant extent. The water from Tigris river is safe for drinking water
  supply schemes after treatment and Euphrates river is not safe this purpo
 se due to high bromine content.\n\nhttp://indico.cern.ch/contributionDispl
 ay.py?contribId=220&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=220&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Retardation behavior of Sr and Cs in Crushed and Intact Rocks：Tw
 o potential LLW repository Taiwan host rocks
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-66@cern.ch
DESCRIPTION:Speakers: Prof. WU\, Ming-Chee (Department of Earth Sciences\,
  National Cheng Kung University\,Taiwan)\nThis study investigates sorption
  and diffusion of Strontium (Sr) and Cesium (Cs) in two potential host roc
 ks (granite from Kinmen Island and basalt from Penghu Island) by using bat
 ch and through-diffusion methods in order to establish a reliable safety a
 ssessment methodology. These methods were applied to crushed and intact ro
 ck samples to investigate the actual geological environment. According to 
 solid-phase analysis\, including X-ray diffraction\, elemental analysis\, 
 auto radiography\, and polar microscopy\, the sorption component primarily
  contained iron–magnesium (Fe–Mg) minerals in basalt and granite. More
 over\, the distribution coefficient (Kd) of Sr and Cs in various concentra
 tions (~10−2–10−7 M) obtained from batch tests indicated a higher so
 rption capacity in basalt than that in granite because of the 10% Fe–Mg 
 mineral content. The diffusion of Sr and Cs both in crushed granite and ba
 salt reach steady state after 110 days and apparent diffusion coefficient 
 (Da) were 3.29×10-11 m2/s (for Sr in crushed granite)\, 4.17×10-12 m2/s 
 (for Sr in crushed basalt)\, 2.86×10-11 m2/s (for Cs in crushed granite)\
 , 1.82×10-12 m2/s (for Cs in crushed basalt)\, respectively. However\, di
 ffusive result (Da) of Sr and Cs in intact rocks was estimated a lower val
 ue than those obtained using crushed rocks. According to the diffusive res
 ults in crushed and intact rocks\, it showed that major retardation of Sr 
 and Cs depended on the microporous structure of tested media\, such as dec
 reases of constrictivity (δ) and increases of tortuosity(τ). In fact\, t
 he solid/liquid (S/L) ratio decreased as is the case when switching from b
 atch to column experiments and the sorption effect on minerals became even
  more negligible in retardation of radionuclide migration.\n\nhttp://indic
 o.cern.ch/contributionDisplay.py?contribId=66&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=66&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Generation of inorganic colloids in the chemical disturbed zone in
  the proximity of a cementitious repository
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-88@cern.ch
DESCRIPTION:Speakers: Dr. FELIPE-SOTELO\, Monica (Loughborough University\
 , UK)\nThe current concept for the disposal of intermediate- and low-level
  waste in the UK involves the placement of grouted waste confined in stain
 less steel canisters in a cementitious repository deep underground. While 
 the cement will buffer the porewater to a highly alkaline pH\, contributin
 g to the retardation of radionuclides by precipitation\, this could potent
 ially create an alkaline plume moving from the repository into the host ro
 ck. The alkaline cement leachate can react with the host rock\, promoting 
 dissolution of some mineral phases\, precipitation of new phases and the g
 eneration of colloids that may affect radionuclide movement within the che
 mically disturbed zone of the host rock.\nThe aim of the present work is t
 o study the generation of inorganic colloids from a generic host rock in c
 ontact with an alkaline plume. An intact core of sandstone has had an arti
 ficial “young” cement leachate (pH 13.10) under CO2-free conditions pu
 mped through it. The solution at the outlet was then sequentially ultrafil
 tered in-line through a rig fitted with \n12 µm\, 1 µm\, 30 kDa and 1 kD
 a membranes. After passing more than 500 pore volumes of the young cement 
 leachate\, the imaging of the filters by Scanning Electron Microscopy (SEM
 ) in combination with X-ray microanalysis showed no evidence of the format
 ion of inorganic colloids under these experimental conditions. On the othe
 r hand\, analysis of the outlet solution by ICP-MS indicates that there is
  significant dissolution of some mineral phases present in the sandstone\,
  however no difference were found between the elemental composition of the
  solution before and after ultrafiltration. Additional tests with artifici
 al colloids indicate that silica and iron oxides colloids are unstable in 
 “young” cement leachate.\n\nAcknowledgments: The authors would like to
  thank NERC for the funding of the BIGRAD consortium.\n\nhttp://indico.cer
 n.ch/contributionDisplay.py?contribId=88&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=88&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Trivalent Actinide/Lanthanide Sorption under Saline Conditions
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-116@cern.ch
DESCRIPTION:Speakers: Dr. RABUNG\, Thomas (Karlsruhe Institute of Technolo
 gy - Institute for Nuclear Waste Disposal\, Germany)\nSorption processes o
 n mineral surfaces play an important role in the retardation behaviour of 
 radionuclides and have to be considered in performance assessment calculat
 ions. However\, almost all available experimental data are restricted to l
 ow ionic strength conditions. Saline conditions are not restricted to solu
 tions relevant to rocksalt formations. Elevated salt concentrations up to 
 6.5 M are also found in sedimentary rocks which are under investigation wi
 thin nuclear waste disposal programs. \nIn the present work\, experiments 
 have been performed with quartz and illite. In all cases sorption of Eu(II
 I) radiolabelled with Eu-152 was studied in batch experiments\, where ioni
 c strength was varied up to 5 M NaCl. Experiments with Cm(III) and the tim
 e resolved laser fluorescence spectroscopy (TRLFS) are directed to obtain 
 detailed information on the metal ion speciation at the mineral surfaces a
 s a function of ionic strength.\nIn all systems we observed a decreasing s
 orption with increasing ionic strength. While for quartz only inner-sphere
  surface complexation is expected for Eu(III)\, outer sphere sorption at l
 ow pH must be considered for illite.\nEu(III) sorption to illite was calcu
 lated by a slightly modified well established non-electrostatic sorption m
 odel\, developed and tested so far only for lower ionic strength condition
 s (2SPNE/CE). The Pitzer formalism was used to calculate activity coeffici
 ents for aqueous species. Model calculations for different ionic strengths
  yield fair agreement with the experimental data. This finding suggests th
 at the shift in sorption edges with increasing ionic strength is basically
  due to a variation of ion activities and a concomitant change in aqueous 
 metal ion speciation. \nTRLFS experiments with Cm(III) indicate no signifi
 cant differences for sorbed inner-sphere Cm(III) complexes at low and high
  ionic strength conditions. Our preliminary study indicates that the modif
 ied non-electrostatic 2SPNE/CE model can be applied to predict sorption of
  trivalent actinide ions also for elevated ionic strength conditions at le
 ast in NaCl dominated solutions.\n\nhttp://indico.cern.ch/contributionDisp
 lay.py?contribId=116&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=116&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Synthesis of new 18F-labelled Porphyrins and their potential aplic
 ation for in vivo Molecular Imaging with PET
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-204@cern.ch
DESCRIPTION:Speakers: Ms. SIMÕES\, Ana (Chemistry Department\, University
  of Coimbra\, Rua Larga 3004-535\, Coimbra\, Portugal)\nMolecular imaging 
 holds the promise of non-invasive assessment for biological and biochemica
 l processes in living subjects using specific imaging tracers.  Positron E
 mission Tomography (PET) is a highly specific and sensitive molecular imag
 ing technique with widespread use for research and clinical application. T
 he majority of PET studies today are performed with molecules labelled wit
 h fluorine-18\, a radionuclide possessing important characteristics includ
 ing a favourable half-life (110 min) and the ability to replace H in organ
 ic molecules.1\nIt’s widely recognised that porphyrins are one of the mo
 st important prosthetic groups in biological systems and porphyrin derivat
 ives have recently found promising biomedical applications in detection an
 d treatment of a variety of tumours due to their affinities for these tiss
 ues in relation with the nature of the side chain and the mechanism of the
 ir physico-chemical action.2-5 In this communication we describe our recen
 t studies on the synthesis of novel sulfonamide substituted meso-tetraphen
 ylporphyrins and automated synthesis of new 18F-labelled porphyrin derivat
 ives\, by fluorination via nucleophilic substitution with K2CO3/K2.2.2/ACN
 . Preliminary biodistribution studies in rats with PET will be presented. 
 We believe our results may open new directions for the development of new 
 theragnostic tools.\n\nAcknowlegments:\nThe authors thank FCT/QREN/FEDER-C
 OMPETE Portugal\; FCT for AVC Simoes PhD grant (SFRH/BD/65699/2009)\; Mari
 a Puigivila\, Carlos Perez\, Mikel González and Aitor Lekuona from CICbio
 maGUNE.\n\nReferences\n\n[1](a) William K. Hagmann\, Journal of Medicinal 
 Chemistry\, 15\, 2008\, 4359\; (b) Didier Le Bars\, Journal of Fluorine Ch
 emistry\, 127\, 2006\, 1488.\n[2] Dabrowski et al.\, ChemMedChem\, 2011\, 
 6\, 1715 \n[3] M. M. M Pereira\, C. J. P Monteiro\, A. V. C. Simões\; et 
 al.\,  J. Porphyrins Phathlocyanines 13\, 2009\, 567.\n[4] Dabrowski et al
 .\, Med. Chem. Commun.\, 3\, 2012\, 502.\n[5] Pereira\, M. M.\; Monteiro\,
  C. J. P.\; Simoes\, A. V. C.\; et al.\, Tetrahedron\, 66\, 2010\, 9545.\n
 \nhttp://indico.cern.ch/contributionDisplay.py?contribId=204&sessionId=26&
 confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=204&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Adsorption of selected fission products on var
 ious forms of TiO<sub>2</sub> nanoparticles.
DTSTART;VALUE=DATE-TIME:20120918T161000Z
DTEND;VALUE=DATE-TIME:20120918T162500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-151@cern.ch
DESCRIPTION:Speakers: Ms. FILIPOWICZ\, Barbara (Institute of Nuclear Chemi
 stry and Technology\, Dorodna 16\, 03-195 Warsaw\, Poland)\nDue to the hig
 h selectivity\, radiation resistance\, thermal and chemical stability\, in
 organic ion exchangers have being widely used in the treatment of reactor 
 coolant and aqueous nuclear wastes. Among others\, inorganic sorbents\, hy
 drous titanium dioxide are proposed as the promising inorganic sorbent for
  the efficient separation of  fission and corrosion products such as 137Cs
 \, 90Sr\, 239\,240Pu\, 60Co\, 65Zn and 54Mn. Recently\, new forms of nanom
 eter sized TiO2 with unique ion exchange properties were obtained. The phy
 sicochemical properties of nanostructured titanates are highlighted and th
 e relation between properties and applications are emphasized. \nIn the pr
 esent work we synthesized and studied ion exchange properties of TiO2 in n
 anotubes\, nanofibers\, nanowires and nanoribbons forms. The TiO2 nanostru
 ctures were synthesized using hydrothermal procedure. Material obtained ha
 s the large specific surface and internal structure of grains. The size an
 d the shape of obtained nanoparticles were characterized by SEM and TEM me
 thods and specific surface by BET technique. \nThe measurements were perfo
 rmed on the titanium dioxide nanotubes (diameter >5 nm\, length >100 nm) n
 anofibers (thickness >7 nm\, length >10 μm)\, nanowires (diameter >5 nm\,
  length >10 μm) and nanoribbons (thickness 5> nm\, length >10 μm). All s
 ynthesized samples were examined for adsorption of 137Cs and 85Sr in 0.1 M
  NaNO3 and KNO3 solutions. Additionally\, kinetics\, the dependence of the
  sodium salt concentration and influence of pH were examined. All nanopart
 icles studied show high affinity for both investigated radionuclides. \nTh
 e affinity of nanotubes for Cs+ and Sr2+ was slightly higher in case of na
 notubes than other TiO2 nanoparticles. The obtained results indicate a wid
 e range of applications TiO 2 nanostructures as adsorbents for the efficie
 nt separation of  fission and corrosion products from nuclear wastes.\nThe
  work was supported by Governmental Strategic Project: Supporting technolo
 gies for the development of safe nuclear power nr SP/J/4/143321/11\n\nhttp
 ://indico.cern.ch/contributionDisplay.py?contribId=151&sessionId=22&confId
 =183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=151&sessionId=2
 2&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Radiolabelling of engineered nanoparticles –
  different strategies for Ag<sup>0</sup>-NP\, TiO<sub>2</sub>-NP and MWCNT
DTSTART;VALUE=DATE-TIME:20120919T145000Z
DTEND;VALUE=DATE-TIME:20120919T150500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-150@cern.ch
DESCRIPTION:Speakers: Dr. FRANKE\, Karsten (HZDR\, Germany)\nRadioactive t
 racers provide a simple and effective tool for transport studies of nanopa
 rticulate materials within environmental samples at laboratory scale. Comp
 ared to classical approaches radiolabelling of nanoparticles (NP) offers a
 dvantages in sensitivity and selectivity together with the possibility of 
 in-situ imaging of transport phenomena. Particularly with regard to quanti
 tative evaluation for transport studies radiotracers allow an easy differe
 ntiation between the elemental/nanoparticulate background concentration an
 d the NP-derived input into an environmental sample. The limiting factor o
 f the use of radiotracers is the possible alteration of experimentally rel
 evant physical/chemical properties of the NP due to the radiolabelling and
  also the stable binding of the tracer on the NP. Depending on the experim
 ental needs (half-life\, decay-mode/radiation)\, different labelling metho
 ds are available. \nThe study aims at the comparison/evaluation of radiola
 belling methods for Ag0-NP\, TiO2-NP and MWCNT:\n\n(1) direct activation o
 f NP due to cyclotron irradiation:\n- Ag0-NP: 107Ag(p\,3n)105Cd --> 105Ag 
 / 107Ag(p\,p2n)105Ag\n- TiO2-NP: 48Ti(p\,n)48V\n- MWCNT: 12C(p\,3d)7Be\n\n
 (2) self-diffusion of radioisotopes: \n- Ag0-NP: 105\,110mAg\n- TiO2-NP: 4
 4\,45Ti\n\n(3) radioiodination\n- MWCNT: 125\,131I\n\n(4) recoil labelling
 :\n- Ag0-NP: 7Li(p\,n)7Be\n- TiO2-NP: 7Li(p\,n)7Be\n- MWCNT: 7Li(p\,n)7Be\
 n\nThe direct irradiation and the recoil labelling were carried out at a S
 canditronix MC40 cyclotron [1\, 2]\, self-diffusion experiments were carri
 ed by means of a Cyclone® 18/9 (IBA molecular) [3]. The methods were test
 ed with respect to labelling yield\, achievable activity concentration\, p
 H-dependent stability of the labelling and the influence on NP-properties.
  Data thus obtained enable an appropriate selection of radiolabelling meth
 ods for different experimental applications.\n\nReferences\n[1] Abbas K\, 
 Cydzik I\, Del Torchio R\, Farina M\, Forti E\, Gibson N\, Holzwarth U\, S
 imonelli F\, Kreyling W (2010) J Nanopart Res 12:2435–2443.\n[2] Holzwar
 th U\, Bulgheroni A\, Gibson N\, Kozempel J\, Cotogno G\, Abbas K\, Simone
 lli F\, Cydzik I (2012) J Nanopart Res 14:880.\n[3] Hildebrand H and Frank
 e K (2012) J Nanopart Res submitted.\n\nhttp://indico.cern.ch/contribution
 Display.py?contribId=150&sessionId=25&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=150&sessionId=2
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Error\, Uncertainty\, and Metrology in Nuclear A
 nalytical Methods
DTSTART;VALUE=DATE-TIME:20120920T070000Z
DTEND;VALUE=DATE-TIME:20120920T072000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-153@cern.ch
DESCRIPTION:Speakers: Dr. LINDSTROM\, Richard (National Institute of Stand
 ards and Technology\, USA)\nNuclear methods have well-established advantag
 es in chemical analysis. Paradoxically\, many of these advantages stem fro
 m the absence of chemistry in the analytical process. Nuclear reactions ar
 e often easier to understand than chemical reactions\, and nuclear methods
  are usually direct\, with simple equations relating the laboratory measur
 ements to the sought-for composition. Neutron activation analysis has rece
 ntly been recognized by the Comité Consultatif pour la Quantité de Mati
 ère as a primary ratio method\, meaning that its results can be traceable
  to the fundamental units of the Système International. For this to be pr
 actically as well as formally true\, an exhaustive search for\, and quanti
 fication of\, sources of bias (errors) and random uncertainty is necessary
  to describe the metrological traceability of a measurement result. The tr
 ansparent interweaving of these issues with economics and fitness for purp
 ose is an integral part of analytical research.\n\nhttp://indico.cern.ch/c
 ontributionDisplay.py?contribId=153&sessionId=27&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=153&sessionId=2
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - TiO<sub>2</sub> nanoparticles as vehicles of <
 sup>212</sup>Pb and <sup>225</sup>Ac for internal radiotherapy
DTSTART;VALUE=DATE-TIME:20120917T104500Z
DTEND;VALUE=DATE-TIME:20120917T110000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-152@cern.ch
DESCRIPTION:Speakers: Ms. LESZCZUK\, Edyta (Institute of Nuclear Chemistry
  and Technology\, Poland)\nThere are only a few a-particle emitting radion
 uclides that have properties suitable for developing therapeutic radiophar
 maceuticals. Unfortunately\, all available a-emitters have serious disadva
 ntages: 211At forms weak bond with carbon atoms in the biomolecule and in 
 the case of 212Bi\, 213Bi and 226Th short half-life often limits the appli
 cation of these nuclides. However\, the short half-life of 212Bi and 213Bi
  could be effectively lengthened by binding the parent radionuclide 212Pb 
 (t1/2 = 10.6 h) or 225Ac (t1/2 = 10 d) to a biomolecule\, thereby effectiv
 ely extending the use of short half-life 212Bi and 213Bi. In addition\, 21
 2Pb/212Bi and 225Ac/213Bi in vivo generator delivers much greater dose per
  unit of administered activity compared to 212Bi and 213Bi alone. \nIn our
  studies we investigated the properties of TiO2 nanoparticles as potential
  carriers of 212Pb/212Bi\, 225Ac/213Bi generators. The TiO2 nanoparticles 
 have special properties like high specific surface and high affinity for c
 ertain cations like mentioned Pb2+\, Bi3+ and Ac3+\, which are useful duri
 ng the labelling process. Commercially available (P25 Degussa) and synthes
 ised in our laboratory nanoparticles were used in experiments. The nanopar
 ticles were characterized by SEM and NanoSight techniques.\nWe obtained hi
 gh yields of labelling (ca. 99%) anatase nanoparticles in case of 212Pb an
 d 225Ac. Afterwards\, the stability of labelled nanoparticles was tested i
 n 0.9 % NaCl\, \n10-3 M EDTA\, solutions of biologically active substances
  (cysteine\, glutathione) and human serum. The leakage of 212Pb or 225Ac a
 nd their daughter radionuclides was not significant in any of solutions\, 
 even when the incubation time was extended to 24 hours. The obtained resul
 ts show high stability of labelled nanoparticles and allow to begin furthe
 r experiments\, which are based on modification of the surface by silane c
 ompounds which enable binding the biomolecules.\n\nhttp://indico.cern.ch/c
 ontributionDisplay.py?contribId=152&sessionId=15&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=152&sessionId=1
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:New analytical method for actinide (Pu\, Am\, U\, Th\, Np) separat
 ion based on diglycolamide resin (DGA)
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-155@cern.ch
DESCRIPTION:Speakers: Ms. GROSKA\, Judit (Radanal Ltd.\, Hungary)\nOne of 
 the most critical part in the treatment of liquid radioactive wastes is th
 e separation process of tervalent actinides\, especially that of Am in aci
 dic solutions. After decades of investigation a new extraction chromatogra
 phic material\, the DGA resin was developed with good extraction propertie
 s for all actinides\, moreover extremely high extractability towards Am1.\
 nOur goal was to separate major and minor actinides\, i.e. U\, Th\, Pu\, N
 p\, Am (Cm) from radioactive waste samples and determine the radionuclides
  by α spectrometry. DGA is a good candidate material for the extraction c
 hromatographic separation of actinides in tetra-\, hexa- and (moreover) in
  tervalent oxidation states due to the high distribution ratios from a wid
 e range of concentration of nitric and hydrochloric acid solutions. It sho
 ws potential for the simultaneous separation of actinides with the use of 
 a single column.\nThe distribution ratios of Th(IV)\, U(VI)\, Pu(IV) and A
 m(III) on DGA have been determined in hydrochloric and nitric acid media1.
  In our laboratory extraction studies were carried out on various oxidatio
 n states of the actinides including Np species and on the effect of severa
 l possible interferences (Ca2+\, Fe2+\, Fe3+\, SO42-\, S2O82-\, S2O52-\, S
 O32-\, N2H4\, NO2-\, I-) by batch and/or column uptake experiments using N
 \,N\,N’\,N’-tetra-n-octyldiglycolamide (DGA Resin\, Normal) produced b
 y Triskem ©2. Based on the measured distribution ratios two new methods w
 ere developed for Th\, U\, Pu\, Am and Np separation in model solutions. O
 xidation state adjustment of actinides was performed before and during on-
 column separation. The methods have been tested by the analysis of liquid 
 radioactive waste samples originating from nuclear power plant using alpha
  spectrometry. Performance parameters of the procedures such as chemical r
 ecoveries and decontamination factors will be presented.\n\n1 Horwitz\, E.
 P.\, McAlister\, D.R.\, Bond\, a. H.\, Barrans Jr.\, R.E. Solvent Extracti
 on and Ion Exchange. 23\, 319-344 (2005)\n2 http://www.triskem-internation
 al.com\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=155&sessi
 onId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=155&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Nuclear Forensics: age determination by the 23
 1Pa/235U ratio
DTSTART;VALUE=DATE-TIME:20120920T075500Z
DTEND;VALUE=DATE-TIME:20120920T081000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-154@cern.ch
DESCRIPTION:Speakers: Dr. MENDES\, Mickael (CEA\, France)\nThe increase of
  traffics of illegal nuclear materials requires the improvement in nuclear
  forensics. The age of the sample\, which corresponds to the determination
  of the date of the last purification\, can give information about its ori
 gin. The aim of this work is to develop an efficient procedure which allow
 s the determination of the age of micro-quantities. Dating micro-quantitie
 s of uranium is possible with two daughter/parent nuclide ratios: 230Th/23
 4U and 231Pa/235U. The procedure of age determination using the 230Th/234U
  ratio is already effective [1\,2]. The development of the 231Pa/235U dati
 ng procedure will allow to confirm results obtained with 230Th/234U. In th
 e same time\, it will provide a survey of the 235U isotope\, i.e. of the e
 nrichment rate.\n	In order to measure such low quantities\, mass spectrome
 tric detection was chosen. Thus\, the isotopic dilution method will be use
 d with the aim of determining the quantity of each isotope. 233Pa is the a
 ppropriate tracer for the detection of 231Pa. Therefore\, 233Pa was milked
  from 237Np\, fixed on AG1-X8 resin.\nA procedure of separation has been e
 stablished in order to date uranium. However\, experimentally\, the separa
 tion of protactinium from uranium was not effective. Consequently\, distri
 bution coefficients of protactinium have to be determined for different me
 dia (HCl and HNO3) and different type of resins (AG1-X8\, TEVA\, U-TEVA\, 
 TRU-SPEC) in order to optimize the procedure.\n	After the determination of
  the distribution coefficients\, the different elements\, i.e. protactiniu
 m and uranium\, will be separated from each other without any residual amo
 unt present in each fraction.\n\nReferences\n\n[1] S. P. LaMont\, G. Hall\
 , J. Radioanal. Nucl. Chem.\, 2005\, 264\, 423\n[2] M. Wallenius\, A. Morg
 enstern\, C. Apostolidis\, K. Mayer\, Anal. Bioanal. Chem.\, 2002\, 374\, 
 379\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=154&sessionI
 d=27&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=154&sessionId=2
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Geochemically anomalous phonolites from Lusatian Mountains\, Czech
  Republic: Possible source materials and processes of their origin
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-157@cern.ch
DESCRIPTION:Speakers: Dr. MIZERA\, Jiří (Nuclear Physics Institute ASCR)
 \nThe study has been aimed at elucidation of source materials and processe
 s leading to formation of anomalous phonolites from the Lusatian Mountains
  (Bohemian Massif\, Czech Republic). For a detailed geochemical study of t
 he phonolites\, various modes of instrumental neutron (short and long time
  irradiation\, including the epithermal and fast neutron mode) and photon 
 activation analyses were utilized. Combination of these modes allowed assa
 ying up to 48 major and trace elements. Strontium and neodymium isotopic c
 ompositions were determined by TIMS.   \nPhonolites represent the subvolca
 nic (hypabyssal) rocks\, which solidified from magma at relatively low tem
 perature and consolidated in shallow depths in the upper bed. They are mos
 tly associated with Tertiary interplate magmatism\, but can originate also
  from differentiation of the upper mantle under the oceanic crust. Phonoli
 tes are strongly depleted by compatible elements as Mg\, Cr\, Fe\, Co\, Ni
 \, Sr\, whereas Na\, K\, Rb\, and Al are enriched.\nThe origin of the stud
 ied phonolites of ca. 30 Ma age is associated with the Lusatian Fault. Com
 pared to phonolites from the Eger Rift in the Bohemian Massif\, contents o
 f incompatible elements Zr\, Hf\,  Nb\, Ta\, Th\, U\, light rare earth ele
 ments\, F and Cl in the Lusatian Mountains phonolites reach extremely high
  values. Their 143Nd/144Nd isotope ratio is monotonous\, corresponding to 
 the upper mantle\, whereas the 87Sr/86Sr ratios reach extreme values up to
  0.8605.\nThe geochemical and isotopic data indicate that the anomalous ph
 onolites may have originated mainly from partial melting of lower crust of
  tonalite-monzonite character or metamorphic rocks – shales with high co
 ntents of\, e.g.\, micas. Participation of matter from the differentiated 
 upper mantle is negligible. The high content of incompatible elements is p
 robably associated\, besides nepheline\, sanidine and other foids\, with a
 ccessory minerals such as zircon or titanite.        \nThis study has been
  supported by the project IAA300130902 of the ASCR Grant Agency.\n\nhttp:/
 /indico.cern.ch/contributionDisplay.py?contribId=157&sessionId=26&confId=1
 83405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=157&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Measurements of γ- and β+-intensities of Ti-45
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-156@cern.ch
DESCRIPTION:Speakers: Mr. KUHN\, Sebastian (Forschungszentrum Jülich\, Ge
 rmany)\nWith rising interest in non-standard PET-nuclides also Ti-45 comes
  into focus. Its low maximum positron energy of 1.04 MeV in combination wi
 th the small amount of γ-rays (most intense at 720.22 keV: 0.15%)  and it
 s advantageous half-life of 184.8 min makes it a suitable nuclide\, especi
 ally for studying  some longer termed processes. There have been first inv
 estigations about its usability as nuclide in positron-emission-tomography
  studies [1\,2]. However\, the corresponding emission intensities have to 
 be known very precisely for medical applications in order to minimize the 
 radiation exposure of the patient and to enhance the diagnostic value by c
 orrect quantification. \nTi-45 was produced via the Sc-45(p\,n)Ti-45 nucle
 ar reaction. Metallic scandium served as target for irradiation at the Bab
 y Cyclotron 1710 of FZ Jülich with protons of 12 MeV incident projectile 
 energy. Copper foils as beam monitors assured the precision of the proton 
 energy and beam current. After dissolving the irradiated target in 4M HCl\
 , radionuclidically pure Ti-45 was isolated in n.c.a. form via ion chromat
 ography\, using 100-200 mesh Dowex 50WX8 resin and 4M HCl as eluent. The c
 o-produced Sc-44 was used as indicator for the absence of scandium. Thin s
 amples were prepared and investigated using positron-counting\, x-ray spec
 trometry and γγ-coincidence measurements to determine the absolute posit
 ron intensity. The γ-ray intensities were ascertained relatively to the p
 ositron emission intensity using HPGe-detector γ-ray spectrometry. \nThe 
 performed - and -coincidence counting resulted in positron emi
 ssion probabilities of 82.4% and 84.9%\, thus supporting the data given in
  the literature [3]. The γ-ray intensities were found to be smaller than 
 those given earlier\, showing deviations of up to 30% [4-6].\n\nIn this st
 udy reproducible decay data could be obtained which specify and improve th
 e β+- and γ-intensity values reported so far\, thus strengthening the re
 liability of these important data for quantification and corrections of PE
 T-measurements. \n\nReferences: 	\n[1]	K. Ishiwata\; T. Ido\; M. Monma\; M
 . Murakami\; M. Kameyama\; H. Fukuda\; T. Matsuzawa\; J. Label. Compds. Ra
 diopharm.\;19\; (1982)\; 1539-1541.\n[2]	A. L. Vavere\; R. Laforest\; M. J
 . Welch\; Nucl Med. Biol.\; 32\; (2005)\; 117-122.\n[3]	T. W. Burrows\; Nu
 clear Data Sheets\; 109\; (2008)\; 171-296. \n[4]	D. Gföller\; A. Flammer
 sfeld\; Z. Physik\; 187\; (1965)\; 490-494.\n[5]	F. T. Porter\; M. S. Free
 dman\; F. Wagner Jr.\; K. A. Orlandini\; Phys. Rev.\; 146\; (1966)\; 774-7
 80.\n[6]	W. M. Zuk\; W. F. Davidson\; M. R. Najam\; M. A. Awal\; Z. Physik
 \; 242\; (1971)\; 93-101.\n\nhttp://indico.cern.ch/contributionDisplay.py?
 contribId=156&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=156&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Natural radionuclides levels in spices and medicinal plants by gam
 ma spectrometry
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-159@cern.ch
DESCRIPTION:Speakers: Dr. JAHOUACH-RABAI\, Wafa (Laboratory de Radiochemis
 try\, National Center of Nuclear Sciences and Technologies (CNSTN)\, Techn
 opole Sidi Thabet\,Tunisia.)\nThis work is a contribution to the valorizat
 ion of nuclear technics for environmental monitoring\, mainly natural radi
 oactivity in edible vegetation. The activities of natural radionuclides in
  major groups of widely used spices and medicinal plants in Tunisia have b
 een investigated. In this aim\, 18 selected samples imported from differen
 t countries were purchased in the dried form of roots\, leaves\, seeds\, b
 arks\, flowers and fruits from local herbalists and farmers. Activity conc
 entrations in all samples were measured by gamma spectrometry.\nSpecific a
 ctivity concentrations measured in the considered samples show different l
 evels in 40K and 238U. These radioanalytical results of 40K showed differe
 nt levels activity concentrations ranging from 168.72 to 1154.1 Bq/kg. The
 y are about 168.72 Bq/kg\, 985.64 Bq/kg\, 480.27 Bq/kg\, 606.15 Bq/kg\, 16
 8.72 Bq/kg and 268.02 to 871.4 Bq/kg respectively for fruits\, roots\, flo
 wers\, leaves\, barks and seeds. The activity of this nuclide is important
  in comparison to other radionuclides\, which is due to the natural abunda
 nce of this essential nutrient in the soil and its high absorption by plan
 ts. Determined concentrations of 238U ranged from 11.02 Bq/kg and 123.18 B
 q/kg. The highest concentrations were obtained for red pepper and fennel c
 haracterized with activity concentrations of 123.18 Bq/kg and 103.04 Bq/kg
  respectively. \nAccording to this study\, it was concluded that many fact
 ors such us plants composition\, mobility of the radionuclides\, climate a
 nd depth distribution of roots control the transfer and uptake of radionuc
 lides from soil into plants.\n\nhttp://indico.cern.ch/contributionDisplay.
 py?contribId=159&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=159&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Diamond Detectors in Transactinide Chemistry
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-158@cern.ch
DESCRIPTION:Speakers: Mr. STEINEGGER\, Patrick (Paul Scherrer Institut / U
 niversity of Bern)\nThe possibilities of on-line thermochromatography expe
 riments with transactinide elements depend on the material of the applied 
 detectors. Si PIN-diodes or Si PIPS-detectors are only usable in a tempera
 ture interval between 90 K and 315 K limited by the electronic band gap of
  Si of about 1.1 eV. In recent experiments using the COLD [1] or COMPACT [
 2] detector setup\, the upper bound of the temperature gradient was limite
 d to 310 K for this reason. Therefore\, the experimental characterization 
 of less volatile elements with higher negative adsorption enthalpies is no
 t feasible. Already the rather volatile mercury with a negative adsorption
  enthalpy on gold of 98 kJ/mol [3] - corresponding to a deposition tempera
 ture of about 430 K using the experimental condition of the COLD system - 
 reveals the constrained range of the currently used setups.\nIn recent yea
 rs the development of chemical vapor deposition (CVD) single crystal diamo
 nds made a considerable progress concerning the available size\, quality\,
  and quantity. CVD single crystal diamond detectors can be heated up to te
 mperatures higher than 500 K without any spectroscopic degradation\, due t
 o their electronic band gap of 5.5 eV [4]. In addition\, they can be opera
 ted under broad daylight or strong IR radiation (e.g. near a heat source) 
 and last but not least\, diamond has one of the highest thermal conductivi
 ties known\, which is important for reproducible properties of the chemica
 l surface temperature.\nWe prepared\, characterized\, and tested different
  types of CVD diamond detector setups\, aiming for an application in futur
 e transactinide chemistry experiments.\n\n\n[1] R. Eichler et al.\, Radioc
 him. Acta 98(3) (2010) 133\n[2] J. Dvořák\, Ph.D. TU Munich (2007)\n[3] 
 B. Eichler et al.\, Radiochim. Acta 33 (1983) 121\n[4] J. H. Kaneko et al.
 \, Nucl. Instr. and Meth. A 422 (1999) 211\n\nhttp://indico.cern.ch/contri
 butionDisplay.py?contribId=158&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=158&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Application of Non-linear Heterogeneity-based Isotherm Models for 
 Charactering Sorption of Cs and Se on Mudrocks
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-62@cern.ch
DESCRIPTION:Speakers: Dr. CHUAN-PIN\, Lee (Department of Earth Sciences\, 
 National Cheng Kung University\, Taiwan)\nIt plays a very important role f
 or characterizing sorption behaviors of cesium (Cs) and selenium (Se) on T
 aiwanese mudrocks to retard the migration of radionuclides from a radioact
 ive waste repository. In this study\, two non-linear heterogeneity-based i
 sotherms\, Langmuir-Freundlich model (LF) and generalized-Freundlich model
  (GF)\, were applied for the evaluation of the sorption characteristics of
  Cs and Se on Taiwanese mudrocks. The batch sorption experiments were carr
 ied out and the experimental data were simulated by LF and GF heterogeneit
 y-based isotherm models. In addition\, the results showed that both of the
  LF and GF models could fit the experimental data more perfectly than the 
 Langmuir one. The heterogeneity of sorption behaviors for Cs and Se could 
 be well characterized by the LF and GF models from the root mean square er
 ror (RMSE) calculation and plot of the affinity spectrum. The results demo
 nstrated that the sorption mechanism of Cs and Se on mudrock is quite diff
 erent and Cs sorption is more heterogeneous and complicated than that in S
 e.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=62&sessionId=
 26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=62&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Characterization of At- and AtO+ species in simple media by high p
 erformance  ion exchange chromatography coupled to gamma detector. Applica
 tion to astatine speciation in human serum.
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-36@cern.ch
DESCRIPTION:Speakers: Dr. SABATIÉ-GOGOVA\, Andrea (Subatech\, Ceisam\, Fr
 ance)\nAstatine is a rare radioelement belonging to the halogen group. Con
 sidering the trace amounts of astatine-211 produced in cyclotrons\, its ch
 emistry cannot be directly evaluated by usual spectroscopic tools. Analyti
 cal tools\, provided that they are coupled with a radioactive detection sy
 stem\, may be an alternative way to study its chemistry. \nIn the present 
 research work\, High Performance Ion Exchange Chromatography (HPIEC) coupl
 ed to a gamma detector (γ) was used to evaluate astatine species under re
 ducing and oxidizing conditions. Also\, to support the reliability of the 
 experiments\, a quantitative analysis using a reactive transport model has
  been done [1]. \nUnder reducing conditions\, results confirm the existenc
 e of one species bearing one negative charge in the pH range of 2-7.5. Wit
 h respect to the other halogens\, its behavior indicates the existence of 
 a negative ion\, astatide At- [2\,3]. The methodology was successfully app
 lied to the speciation of the astatine in human serum. Under fixed experim
 ental conditions (pH 7.4-7.5 and redox potential of 250 mV/ENH) astatine e
 xists mainly as astatide At- and does not interact with the major serum co
 mponents. Also\, the method might be useful for the in vitro stability ass
 essment of 211At-labelled molecules potentially applicable in nuclear medi
 cine. Under oxidizing and acidic pH conditions\, a peak corresponding to o
 ne species holding one positive charge\, in agreement with the literature 
 proposed species [4\,5]\, has been shown. It was defined as AtO+. A change
  in speciation occurs as the pH changes from 1 to 4. Also\, starting with 
 At- at pH 7 under reducing conditions\, a change in speciation was observe
 d as the potential increases. In both experiments\, this species was elute
 d in the void volume showing neutral species. A complementary experimental
  competition method based on liquid/liquid extraction and modeling [6\,7] 
 has confirmed the exchange of one proton indicating the probable formation
  of AtO(OH). The thermodynamic hydrolysis constant obtained by quasi-relat
 ivistic quantum calculations [7\,8] has also confirmed this species.\n\n1.
  A. Sabatié-Gogova\, J. Champion\, S. Huclier\, N. Michel\, F. Pottier\, 
 N. Galland\, Z. Asfari\, M. Chérel and G. Montavon\, Analytica Chimica Ac
 ta 2012\, 721\, 182.\n2. G.-J. Meyer\, Chromatographie Trägerfreier Anorg
 anisher Formen von Jod-123 und Astat-211 und ihre Verwendung zur Halogenie
 rung von Uracil and Desoxyuridin\, Berichte Nr.1076\, Kernforschungsanlage
  Jülich\, Jülich\, 1974.\n3. K. Roessler\, W. Tornau\, G. Stoecklin\, J.
  Radioanalytical Chemistry 1974\, 21\, 199–209.\n4. A. Cavallero\, K. Ro
 ssler\, Radiochimica Acta 1989\, 47\, 113–117.\n5. D. K. Tyung\, I. V. D
 udova\, V. A. Khalkin\, Radiokhimiya 1973\, 16 (4)\, 548-553.\n6. J. Champ
 ion\, C. Alliot\, S. Huclier\, D. Deniaud\, Z. Asfari and G. Montavon\, In
 organica Chimica Acta 2009\, 362\, 2654-2661.\n7. J. Champion\, C. Alliot\
 , E. Renault\, B. M. Mokili\, M. Cherel\, N. Galland and G. Montavon\, The
  Journal of Physical Chemistry A 2010\, 114\, 576-582.\n8. J. Champion\, M
 . Seydou\, A. Sabatié-Gogova\, E. Renault\, G. Montavon and N. Galland\, 
 Physical Chemistry Chemical Physics 2011\, 13\, 14984-14992.\n\nhttp://ind
 ico.cern.ch/contributionDisplay.py?contribId=36&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=36&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Use of radioactive targets for production of the
 rapy radionuclides at the Brookhaven Linac Isotope Producer
DTSTART;VALUE=DATE-TIME:20120919T104000Z
DTEND;VALUE=DATE-TIME:20120919T110000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-238@cern.ch
DESCRIPTION:Speakers: Dr. MAUSNER\, Leonard (Brookhaven National Laborator
 y\, USA)\nOur program is presently investigating the production of 67Cu\, 
 86Y and 225Ac. The half life and beta emission of 67Cu have long been reco
 gnized as attractive for radioimmunotherapy. The short lived positron emit
 ter 86Y should be useful for patient dosimetry measurement prior to high d
 ose 90Y immunotherapy. The alpha emitter 225Ac may be attractive for treat
 ment of micrometastases\, but supply from its 229Th parent is extremely li
 mited. The reaction routes we have chosen for these products are 68Zn(p\,2
 p)67Cu at proton energy above 100 MeV\, 86Sr(p\,n)86Y at proton energy of 
 15 MeV\, and 232Th(p\, spall)225Ac at proton energy above 130 MeV\, respec
 tively.  The 68Zn and 86Sr targets are expensive enriched isotopes for whi
 ch recovery and reuse are needed for economical production.  After the fir
 st irradiation these materials will contain longer lived radioactive 65Zn 
 and 85Sr.  Similarly 232Th is slightly radioactive to start. Standard targ
 et claddings at BLIP are sealed by electron beam welding\, but the use of 
 this method for radioactive material is not feasible.  Therefore a target 
 cladding that can be sealed remotely in a hot cell was required.  The fina
 l capsule design comprises two aluminum disks with thin machined windows t
 hat are held together with 8 screws\, situated on the periphery of the tar
 get and sealed with a silver coated stainless steel “C” ring.  Calcula
 tions of thermal and mechanical properties that guided the capsule design 
 will be presented\, as well as initial experimental results.\n\nhttp://ind
 ico.cern.ch/contributionDisplay.py?contribId=238&sessionId=24&confId=18340
 5
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=238&sessionId=2
 4&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Radiochemistry of Astatine-211:  Application to 
 Alpha Particle Targeted Radiotherapeutics
DTSTART;VALUE=DATE-TIME:20120917T132000Z
DTEND;VALUE=DATE-TIME:20120917T134000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-239@cern.ch
DESCRIPTION:Speakers: Prof. ZALUTSKY\, Michael (Duke University\, USA)\nTh
 e heavy halogen 211At\, first proposed for use in α-particle targeted rad
 iotherapy more than 30 years ago\, continues to be one of the most promisi
 ng radionuclides for this purpose.  Its 7.2-h half life provides some flex
 ibility with regard to the range of molecular carriers with compatible pha
 rmacokinetics including antibody fragments\, peptides\, affibodies and org
 anic molecules.  Its diverse chemistry\, possessing both halogen and metal
 lic characteristics has permitted its incorporation into a wide array of t
 argeting vehicles.  Most strategies have relied on its chemical similarity
  to iodine to provide a useful point of departure\, with astatodemetallati
 on reactions being a notable example.  However\, the relatively low carbon
 -astatine bond strength is challenging\, and has lead to the exploration o
 f alternative approaches including those involving higher oxidation states
  of astatine\, complex formation and the labelling of boron clusters.  Ano
 ther important issue from a radiochemistry perspective is the need to comp
 ensate for radiolysis-mediated effects including destruction of reactants\
 , reaction with solvent\, and alteration in astatine oxidation state\, tha
 t can occur at the activity levels required for targeted radiotherapy in p
 atients.  For protein-based targeting vehicles\, specific activity also ca
 n be a critical particularly in situations where the average number of rec
 eptors per tumor cell is relatively low and heterogeneous dose deposition 
 can be problematic.  Finally\, if 211At-labeled radiopharmaceuticals are t
 o have a meaningful impact\, the ability to produce clinically relevant le
 vels of 211At that can be shipped to remote locations in chemically tracta
 ble form must be demonstrated.  Hopefully\, advances in the radiochemistry
  of 211At will facilitate the initiation of more clinical trials involving
  this promising α-particle emitting radionuclide.  Our own efforts in tha
 t regard currently are directed at developing the methodologies required t
 o initiate clinical evaluation of meta-[211At]astatobenzylguanidine and 21
 1At-labeled trastuzumab in patients with neuroblastoma and breast cancer n
 eoplastic meningitis\, respectively.\n\nhttp://indico.cern.ch/contribution
 Display.py?contribId=239&sessionId=17&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=239&sessionId=1
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Radiochemical separation of no-carrier-added 97Ru and 95Tc produce
 d by 12C-induced reaction on natural yttrium target
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-67@cern.ch
DESCRIPTION:Speakers: Prof. LAHIRI\, Susanta (Chemical Sciences Division\,
  Saha Institute of Nuclear Physics\, 1/AF Bidhannagar\, Kolkata 700064\, I
 ndia)\nDue to favourable nuclear and chemical properties\, the radionuclid
 es\, 97Ru\; 2.83 d\, -rays: 215.70 keV (85.62 %) and 324.49 keV (10.79 
 %) and 95Tc\; 20.0 h\, -rays: 765.789 keV (93.8 %)\, have been found pr
 omising for the investigation of delayed physico-chemical and biological p
 rocesses. Various 97Ru/95Tc-labelled complexes have also been proposed for
  this purpose. Production of high purity radionuclides is therefore import
 ant. So far they have been produced either by light charged particle induc
 ed reactions or by neutron activation method. This paper illustrates simul
 taneous production of 97Ru and 95Tc in a heavy ion induced reaction and th
 eir subsequent separation from the bulk by ion exchange technique. A natur
 al yttrium foil was irradiated by 75 MeV 12C6+ ions for 3.5 h. Thick targe
 t yields of 514 and 338 kBq/A-h were achieved for 97Ru and 95Tc respect
 ively at the end of bombardment. The target was dissolved in 0.1 M HCl\, s
 piked with 88Y (106.6 d)\, evaporated to dryness\, and residue was taken i
 nto 0.01 M HCl. The nca 97Ru and 95Tc was then radiochemically separated f
 rom bulk yttrium by liquid-liquid extraction (LLX) using liquid anion exch
 anger trioctylamine (TOA) and liquid cation exchanger di-(2-ethylhexyl)pho
 sphoric acid (HDEHP) dissolved in cyclohexane from HCl solution. More than
  98% nca 95Tc was extracted into TOA phase possibly forming anionic specie
 s leaving nca 97Ru and yttrium in aqueous phase.  Quantitative separation 
 of 97Ru was achieved while bulk yttrium was extracted quantitatively into 
 HDEHP (1-10%) from 0.1 M HCl. The technique offers efficient chemical sepa
 ration of the products (97Ru and 95Tc) resulting very high separation fact
 ors (~106).\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=67&s
 essionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=67&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - A renaissance of radionuclide generators for ver
 satile application
DTSTART;VALUE=DATE-TIME:20120917T092000Z
DTEND;VALUE=DATE-TIME:20120917T094000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-234@cern.ch
DESCRIPTION:Speakers: Prof. ROESCH\, Frank (University of Mainz\, Germany)
 \nIntroduction: Radionuclide generator systems continue to play a key role
  in providing both diagnostic and therapeutic radionuclides for various ap
 plications in nuclear medicine\, oncology and interventional cardiology. I
 n parallel to the well established 99Mo/99mTc generator used for SPECT ima
 ging\, new generators for PET/CT imaging attract attention. In particular 
 the 68Ge/68Ga system (68Ge: t½ = 270.95 d\; 68Ga: t½ = 67.7 min\, β+ br
 anching = 89.1%) has found impressive and established clinical application
 \, the 44Ti/44Sc generator (44Ti: t½ = 60 a\; 44Sc: t½ = 3.97 h\, β+ br
 anching = 94.3) represents a promising system providing a longer-lived dau
 ghter\, and a 140Nd/140Pr system (140Nd: t½ = 3.37 d d\; 140Pr: t½ = 3.3
 9 min\, β+ branching = 51.0%) may be used in terms of an in vivo generato
 r.\nChallenges: (1) Different to the established 99Mo/99mTc generator used
  for SPECT imaging\, new generators for PET/CT such as the 68Ge/68Ga syste
 m [1] and the 44Ti/44Sc generator ask for special generator designs becaus
 e of the long half-life of the parent nuclide. Both represent secular equi
 librium systems (different to the transient 99Mo/99mTc generator) as well 
 as long shelf-life. Both generators may be used over periods of many month
  and many years\, respectively. Still the elution yield of the daughter sh
 ould be high and the breakthrough of the parent low. \n(2) While the gener
 ators mentioned all separate parent and daughter nuclides due to different
  chemical properties of the chemical elements involved\, i.e. Mo vs. Tc\, 
 Ge vs. Ga\, Ti vs. Sc)\, the 140Nd/140Pr system involves two neighbored la
 nthanides of very similar chemical behavior.\nExperiments and Conclusion: 
 (1) It appears to be a rather general feature of radionuclide generators b
 ased on longer-lived parent nuclides\, that effective elution modes [2] as
  well as post-elution processing [3] are mandatory. With those aspects man
 aged in an effective way\, the radionuclide generator systems may be tuned
  to medical systems. This was demonstrated in detail for the 44Ti/44Sc rad
 ionuclide generator. Very low breakthrough of 44Ti and high yield of 44Sc 
 is guaranteed by sophisticated generator designs (anion exchange resin as 
 column material\, HCl / oxalic acid mixtures for elution)\, but in additio
 n by a scheme of reverse elution directions. Particular attention was paid
  to the application of a reverse elution mode\, which helps to retain the 
 parent nuclide along the chromatographic column even after many hundred el
 utions. A 5 mCi generator provides about 170 MBq of 44Sc after direct elut
 ion and about 150 MBq following online post-processing similar to the 68Ge
 /68Ga generator. The final content of 44Ti is as low as  107.. \n(2) With 
 no-carrier-added 140Nd produced by irradiations of CeO2 and Pr2O3 targets 
 [4]\, an efficient 140Nd/140Pr radionuclide generator system was developed
  and evaluated. The principle of the radiochemical separation is based on 
 physico-chemical transitions (hot-atom effects) of the daughter 140Pr foll
 owing the electron decay process of 140Nd. The parent radionuclide 140Nd(I
 II) is quantitatively adsorbed on a solid phase matrix in the form of 140N
 d-DOTA-conjugated complexes. 140Nd generated is released from the 140Pr-DO
 TA core as an ionic species. It is easily separated using low volumes of v
 arious aqueous eluents. The elution yield is at least 93%\, if an optimize
 d eluent\, such as DTPA solution is applied. The system remains stable at 
 least over three half-lives of 140Nd\, with high radiolytic stability and 
 low 140Nd breakthrough of ca. 0.025% [5].\n\n[1] Roesch F\, Riss PJ. The r
 enaissance of the 68Ge/68Ga radionuclide generator initiates new developme
 nts in 68Ga radiopharmaceutical chemistry. Curr Top Med Chem. 10/16 (2010)
  1633-68.\n[2] Filosofov DV\, Loktionova NS\, Rösch F. A 44Ti44/Sc radion
 uclide generator for potential application of 44Sc-based PET-radiopharmace
 uticals. Radiochimica Acta 98/3 (2010) 149-156\n[3] Pruszyński M\, Loktio
 nova NS\, Filosofov DV\, Rösch F. Post-elution processing of 44Ti/44Sc ge
 nerator-derived 44Sc for clinical application. Appl Radiat Isot. 68/9 (201
 0) 1636-1641\n[4] Rösch F\, Brockmann J\, Lebedev NA\, Qaim SM. Productio
 n and radiochemical separation of the Auger electron emitter 140Nd. Acta O
 ncologica\, 39 (2000) 727-730\n[5] Zhernosekov KP\, Filosofov DV\, Qaim SM
 \, Rösch F. A 140Nd/140Pr radionuclide generator based on physico-chemica
 l transitions in 140Pr complexes after electron capture decay of 140Nd-DOT
 A. Radiochim Acta 95 (2007) 319-327.\n\nhttp://indico.cern.ch/contribution
 Display.py?contribId=234&sessionId=15&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=234&sessionId=1
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Update of GEN-IV reactors and lead cooled reacto
 rs
DTSTART;VALUE=DATE-TIME:20120918T125500Z
DTEND;VALUE=DATE-TIME:20120918T133000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-235@cern.ch
DESCRIPTION:Speakers: CINOTTI\, Luciano (M.E.Rivus s.r.l\, Italy)\nThe pat
 h to develop advanced nuclear reactors that are superior to current system
 s is described in the 2002 Roadmap Report entitled “A Technology Roadmap
  for Generation IV Nuclear Energy Systems” which was prepared by the Gen
 eration IV International Forum (GIF) in 2002. This roadmap defined challen
 ging technology goals for advanced reactor systems in four major areas:\n
 •	Sustainability\, \n•	Economics\, \n•	Safety and reliability\, and\
 n•	Proliferation resistance and physical protection.\n\nOf the six syste
 ms identified as promising by the GIF roadmap\, the three inherently fast 
 reactors are the GFR\, SFR and LFR. Fast reactor systems\, offer the poten
 tial for great efficiency in fuel utilization\, and can be considered a su
 perior option to achieve the goal of long-term sustainability. \n\nThe Fuk
 ushima accidents have drawn increased attention to the need for advanced r
 eactors to be resilient in the face of unforeseen and/or severe accident c
 onditions. In this context\, the intrinsic characteristics of lead as a co
 olant lead to particular advantages of the LFR as an advanced reactor tech
 nology to meet present and future needs.\n\nAn extensive R&D program relat
 ed to heavy-metal cooled systems was recently initiated in Europe. These e
 fforts\, conducted under the of EURATOM projects of the 6th and 7th Framew
 ork Programme\, are addressing many of the most important issues related t
 o the viability of the LFR.\n\nIn the ELSY project of the 6th Framework Pr
 ogramme\, effort has been spend to improve  compactness for economics and 
 to improve the plant performance with respect to seismic loads. The abovem
 entioned goals require large innovation of the primary system configuratio
 n and the use of innovative components which need extensive experimental c
 ampaigns devoted to qualification and functional confirmation.\n\nIn Europ
 e the Romanian Government has  expressed interest to Euratom in hosting th
 e Demo of the LFR. Russia maintains interest in LFR and recently Chinese O
 rganizations have started  involving in LFR technology.\n\nhttp://indico.c
 ern.ch/contributionDisplay.py?contribId=235&sessionId=19&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=235&sessionId=1
 9&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - High power superconducting proton accelerators f
 or ADS and Gen-IV
DTSTART;VALUE=DATE-TIME:20120918T151000Z
DTEND;VALUE=DATE-TIME:20120918T153000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-236@cern.ch
DESCRIPTION:Speakers: Prof. PAGANI\, Carlo (University of Milano and INFN 
 LASA\, Italy)\nAccelerator Driven Systems (ADS) have been considered and d
 eeply studied since mid nineties as a possible solution to transmute long 
 lived minor actinides and fission products in order to reduce the radio-to
 xicity of nuclear waste repository. The ADS scheme has been one of the dri
 ving objective for the strong development since then of the design of high
  intensity proton accelerators with MW beam power. An accelerator design b
 ased on stringent availability and reliability requirements has been the c
 onsequence of the combination of a sub-critical reactor with a particle ac
 celerator. While the ADS concept is not considered anymore as the principa
 l solution for the nuclear waste problem\, it is still part of the Gen-IV 
 scenario and the high power superconducting linear accelerators are being 
 continuously developed for spallation neutron sources\, particle physics a
 nd material irradiation facilities for fusion reactor.\n\nhttp://indico.ce
 rn.ch/contributionDisplay.py?contribId=236&sessionId=22&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=236&sessionId=2
 2&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - ARRONAX: on the way to the production of radio-i
 sotopes with high-power targets
DTSTART;VALUE=DATE-TIME:20120919T102000Z
DTEND;VALUE=DATE-TIME:20120919T104000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-237@cern.ch
DESCRIPTION:Speakers: Dr. HADDAD\, Ferid (Subatech / ARRONAX\, France)\nAR
 RONAX\, acronym for "Accelerator for Research in Radiochemistry and Oncolo
 gy at Nantes Atlantique"\, is a high energy (70 MeV) and high intensity mu
 lti-particle cyclotron located in Nantes (France). It is designed to be ab
 le to extract two proton beams simultaneously (dual beam mode) up to 2*375
 µA. Beams can be delivered into 6 experimental vaults: Four are devoted t
 o radionuclide production and equipped with an irradiation station connect
 ed to our hot cells via a pneumatic system\; one contains a neutron activa
 tor developed in collaboration with the AAA company whereas the last one i
 s used for basic research with low intensity beam (alpha radiolysis\, radi
 obiology and physics). \nARRONAX main activity is non-conventional radiois
 otope production for nuclear medicine for both therapeutic use (67Cu\, 47S
 c and 211At) and imaging (82Sr/82Rb and 68Ge/68Ga generators and 64Cu\, 44
 Sc).\n\nAs a first step\, our work has been focused on the production of s
 trontium-82\, copper-64 and astatine-211. For that purpose\, we have devel
 oped our own targets and modified the irradiation stations\, purchased fro
 m IBA\, to meet our requirements and lower the beam power density on targe
 t. With these changes\, it is possible to irradiated deposit (Copper-64 or
  Astatitne-211) as well as encapsulated targets. These changes have allowe
 d producing strontium-82 from RbCl target using 2*95 µA proton beams maki
 ng ARRONAX one of the few places in the world able to produce this isotope
  for commercial use. These changes will also allow a scale up of our Coppe
 r-64 production. In the case of Astatine-211\, an additional beam energy d
 egrader has been designed and mounted on one of the beam line and is prese
 ntly under testing.\n \nIn order to further increase the beam intensity on
  our targets\, we plan to play with all the available parameters. In the c
 ase of Strontium-82\, we are planning to change the target material in col
 laboration with INR Troitsk (Russia). Indeed\, Rb metal is offering higher
  production yield and better thermal conductivity than RbCl. We may also t
 ry the wobbling of the beam. Finally we are thinking on a design of a new 
 target station able to handle larger beam spot on target (we are currently
  limited to 20 mm in diameter). \nAll these changes will help us to take a
 dvantage of the high intensity available on our cyclotron.\n\nThe cyclotro
 n ARRONAX is supported by the Regional Council of Pays de la Loire\, local
  authorities\, the French government and the European Union\n\nhttp://indi
 co.cern.ch/contributionDisplay.py?contribId=237&sessionId=24&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=237&sessionId=2
 4&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Chemical Decontamination\, at Field\, after 137Cs Accident at Goia
 nia\, Brazil
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-230@cern.ch
DESCRIPTION:Speakers: Prof. MEDEIROS\, Joao Alfredo (Universidade Federal 
 do Rio de Janeiro\, Brasil)\nIn1987 to 1988\, we were in charge of chemica
 l decontamination of different materials\, from soils\, roads\, hospitals\
 , schools\, houses indoor\, house-wares and roofs to people\, and their ur
 ines and feces\, and water\, highly contaminated with 137-Cs from a radiot
 herapy device (1300 Ci or 48\,1 TBq)\,  robbed from a deactivated hospital
  in demolition\, in Goiania. The source structure we decontaminate weighed
  304 Kg\, the complete device weighed about 800 Kg\, and could not have be
 en put in a hand car\, by 3 people\, as was published. People dismounted t
 he device in a junkyard\, contaminated a lot of areas and materials in thr
 ee junkyards\, and took most of the 137-CsCl source to their homes\, fasci
 nated with the phos-phorescent blue light. When people were sick and burnt
 \, they washed out the materials of original source \, to the garden. Afte
 r 25 years it is important to present and discuss the accident and the che
 mical solutions to the problem of sprayed CsCl from the original source\, 
 by common people\, water and dust\, due to high water solubility and chemi
 cal interactions with clay minerals and K-containing materials. Some infor
 mation about the chemical  decontamination work was published in the CNEN-
 IAEA Goiania Report\, based in our internal report (1988).  In NRC 7 we in
 tended to present our work\, but it was not possible to participate of the
  conference. In the present work we present and discuss chemical decontami
 nation of different materials at field. Very often it is necessary to atta
 ck chemically the materials to let Cs+  available. The best ion exchange m
 aterial for Cs+ is FeKFe(CN)6 (K Prussian Blue\, or KPB) and not K4Fe(CN)6
   (PB)  used in “Radiogardase” capsules.  Al3+ ions coagulate coloidal
  materials\, H+ attack oxides and carbonates\, K+ substitute Cs+ and KPB e
 xchanges K+ by Cs+. To liberate Cs+ from dust\, soils\, cements\, the best
  solutions are KAl(SO4)2 solutions\, acidified with HCl. For granites it i
 s better to use HF solutions\, to remove Cs from fluorspat. Urine and fece
 s were decontaminated with Resin/KPB. Resin/KPB is effective to decontamin
 ate Cs+ hands and feet\, instead of ingesting Radiogardase capsules\, wait
 ing Cs+ to go in the blood stream to be exchanged at the intestines. We pr
 oduce KPB at field\, in suspensions or supported in cation exchange resins
 \, in wool towels\, is EPU foams  and in t-shirts. Published reports with 
 decontamination methods to decontaminate materials and a city (Harshaw Rep
 ort) \, with NH4Cl or NH4NO3 were too light and slow. Process had to be mu
 ch faster and effective\, and had to take in account the chemical composit
 ion of every material and provide ion exchange to remove Cs+ ions.\n\nhttp
 ://indico.cern.ch/contributionDisplay.py?contribId=230&sessionId=26&confId
 =183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=230&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Conceptual design of a low power ADS with a 70 M
 eV proton beam for reasearch and training
DTSTART;VALUE=DATE-TIME:20120918T145000Z
DTEND;VALUE=DATE-TIME:20120918T151000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-231@cern.ch
DESCRIPTION:Speakers: Dr. SARACCO\, Paolo Giovanni (Istituto Nazionale di 
 Fisica Nucleare\, Sez. Genova\, Italy)\nIn the framework of research on ge
 neration IV reactors\, it is very important to have the\nopportunity of us
 ing infrastructures specifically dedicated to the study of fundamental\npa
 rameters in kinetics and/or dynamics of future\, fast-neutron based\, reac
 tors\, a\ncapability not available for presently available zero-power prot
 otypes.\n\nWe propose the conceptual design of an ADS with high safety sta
 ndards\, to be used as\nwell as a training facility\, but also good flexib
 ility to allow for an wide range of\nmeasurements: safety is guaranteed by
  limiting both the power of the system to be less\nthan 500 kW and the neu
 tron multiplication coefficient to be around 0.95\, by using\nplutonium-fr
 ee fuel and diffusion by a solid lead matrix.\nLead has been chosen by con
 sidering this prototype to be a useful step towards the\ndesign of future 
 LFR\, as well as because it allows a harder neutron spectrum\, to\nfacilit
 ating tests on actinides fission\, as well\n\nThe system is intrinsically 
 subcritical and it needs an external neutron source to be\nsustained.\nSpe
 cific target of the conceptual design is to optimize design features of th
 e core in\nsuch a way to meet previous requirements with the use of commer
 cially available\naccelerator to reduce design costs and increase reliabil
 ity.\n\nThe conceptual design considers 88 active elements made by a solid
  lead matrix of\ndimensions 92X92X1200 mm.\, each containing 81 uranium ox
 ide fuel rods\, enriched at 20%\nof U235. Protons\, coming from a continuo
 us cyclotron of 70 MeV in energy and 1 mA in\nbeam current\, are converted
  into neutrons by a beryllium target. Cooling is provided by\nhelium gas\,
  transparent to neutron and not subject to activation.\n\nhttp://indico.ce
 rn.ch/contributionDisplay.py?contribId=231&sessionId=22&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=231&sessionId=2
 2&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Determination of the isotopic ratio <sup>236</su
 p>U/<sup>238</sup>U in environmental samples
DTSTART;VALUE=DATE-TIME:20120921T064000Z
DTEND;VALUE=DATE-TIME:20120921T070000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-232@cern.ch
DESCRIPTION:Speakers: Prof. WALLNER\, Gabriele (Inst. of Inorganic Chemist
 ry\, Univ. of Vienna\, Währingerstr. 42\, A-1090 Vienna\, Austria)\n236U 
 with a half-life of 2.3∙107 years is produced via thermal neutron captur
 e on 235U. In nature these neutrons may result from (α\,n) reactions on l
 ighter nuclides\, spontaneous fission of 238U\, induced fission of 235U an
 d at the Earth surface they are part of the cosmic rays. Only small amount
 s of 235U are produced naturally from uranium in ores\, soils and rocks\, 
 but a huge amount is produced in nuclear power plants. While naturally 236
 U occurs in ultra trace concentration in the environment with an expected 
 isotopic ratio of 236U/238U in the order of \n10-14 to 10-13(1)\, nowadays
  the ratio measured in surface samples is clearly elevated due to the anth
 ropogenic input.\nFor the analysis of the 236U/238U ratio\, water samples 
 from rivers and creeks were collected in the alpine region of Austria\, fr
 om the Danube\, the Black Sea\, Irish Sea\, and from the Atlantic and Paci
 fic Ocean. From areas in Salzburg and from the clean air site LaPalma Isla
 nd\, Spain\, also soil samples were investigated. Retrospective 236U level
 s were measured in the antlers of red deer. Natural ratios without any ant
 hropogenic contamination were measured in uranium ore and yellow cake samp
 les from Australia\, Brasil and Canada.\nAfter a pre-concentration and an 
 anion exchange step the uranium fraction was \nco-precipitated with NdF3 a
 nd thin sources were prepared for α-spectrometry to determine the activit
 y ratio of 234U/238U and the chemical yield. Afterwards these filters were
  reprocessed for the analysis of the isotopic ratio 236U/238U by AMS (Acce
 lerator Mass Spectrometry) (2). The special aim of our research was the ch
 aracterization of the 236U/238U ratio in environmental samples\, and to in
 vestigate the contribution from anthropogenic sources.\n\nREFERENCES\n\n1)
  P. Steier\, M. Bichler\, L.K. Fifield\, R. Golser\, W. Kutschera\, A. Pri
 ller\, F. Quinto\, S. Richter\, M. Srncik\, P. Terrasi\, L. Wacker\, A. Wa
 llner\, G. Wallner\, K.M. Wilcken\, E.M. Wild\, NIM B 266 (2008) 2246.\n\n
 2) C. Vockenhuber\, I. Ahmad\, R. golser\, W. Kutschera\, V. Liechtenstein
 \, A. Priller\, P. Steier\, S. Winkler\, Int. J. Mass Spectrom. 223-224 (2
 003)713.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=232&ses
 sionId=30&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=232&sessionId=3
 0&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - <sup>90</sup>Y and <sup>177</sup>Lu labelled pep
 tides for PRRT: nuclear and radiochemical aspects
DTSTART;VALUE=DATE-TIME:20120917T094000Z
DTEND;VALUE=DATE-TIME:20120917T100000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-233@cern.ch
DESCRIPTION:Speakers: Dr. CHINOL\, Marco (European Institute of Oncology\,
  Italy)\, Dr. PAPI\, Stefano (European Institute of Oncology\, Italy)\nSom
 atostatin analogues designed to target tumor cells over-expressing somatos
 tatin receptors have been radiolabelled with 90Y- and 177Lu for peptide re
 ceptor radionuclide therapy (PRRT). Clinical trials evidenced large patien
 t variability as regards tumor and organs uptake\, thus sustaining the nee
 d of tailored dosimetry\, for a treatment course with improved safety and 
 efficacy. However\, Yttrium-90 does not decay with emission of a γ photon
  for imaging and cannot be used to estimate radiation dosimetry. Indium-11
 1\, which can be used for imaging has been employed as a surrogate. In cas
 e of 177Lu-peptide therapy\, its gamma-rays enable imaging\, dosimetry\, a
 nd therapy with the same compound.  \nThe radiopharmaceuticals used for PR
 RT have in common a high renal activity concentration and  kidneys have be
 en identified as dose-limiting organs for PRRT\, in particular during ther
 apy with 90Y-DOTATOC. Accurate kidney dosimetry plays a key role for the a
 ssessment of radiation nephropathy. \nThe optimal conditions for radiolabe
 lling DOTA-peptides with 90Y and 177Lu have been evaluated. Reaction kinet
 ics were found to be optimal at pH 4-4.5\, with a steep decrease at lower 
 pH. The binding kinetics are time- and temperature-dependent\, the reactio
 ns being completed after 20 min at 80 ºC. The highest specific activity (
 AS) of  90Y and 177Lu correspond to a mol/mol ratio of DOTA over nuclide o
 f 3½ and 6\, respectively. \nIn general\, at constant radiolabeling AS th
 e RCP increased proportionally with 177Lu AS\, whereas at constant 177Lu A
 S the RCP steeply decreased with increasing radiolabeling AS.\nIn conclusi
 on\, DOTA conjugated peptides can be efficiently radiolabelled at high AS 
 (>50 MBq/nmol) by 177LuCl3 up to one half-life from production\, consideri
 ng that the standard AS at production of commercially available 177Lu is g
 enerally > 740 GBq/mg.\n\nhttp://indico.cern.ch/contributionDisplay.py?con
 tribId=233&sessionId=15&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=233&sessionId=1
 5&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Improvement of Detection Limits for Gamma-Ray Emitting Naturally O
 ccurring Radionuclides in Drinking Water and Biological Materials by Instr
 umental Analysis using Compton Suppression Spectrometry
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-224@cern.ch
DESCRIPTION:Speakers: Prof. CHATT\, Amares (Dalhousie University\, Canada)
 \nThe instrumental measurement of very low activities from naturally occur
 ring radioactive materials (NORM) by gamma-ray spectrometry requires the u
 se of detection systems with the lowest possible external activity. Genera
 lly\, lead shielding and special detector construction materials are used 
 for this purpose. In our laboratory\, we have combined a lead shield and a
  Compton suppression system (CSS) to lower the external background activit
 y. The external background was evaluated by first counting the empty detec
 tor for 24 h without the lead shielding in conventional mode (A). Then the
  same procedure was repeated with the lead shield (B). A third counting wa
 s done using the CSS and the Pb shield (C). A background reduction factor 
 of approximately 3 was obtained by comparing the spectra collected using s
 ystems (A) and (B). When the conventional and the CSS with Pb shielding (i
 .e. B and C) were compared\, the average background reduction factor was a
 bout 16. It was then possible to identify many radionuclides in tap water\
 , well water\, spring water\, mussel tissues and oyster tissues. For examp
 le\, the following radionuclides were detected in a canned tuna sample: (i
 ) 234U\, 234Th\, 230Th\, 214Pb\, and 214Bi belonging to the 238U decay ser
 ies\; (ii) 235U\, 231Th\, 231Pa\, and 227Th of 235U decay series\; and (ii
 i) 228Ac\, 228Th\, 212Pb\, and 214Bi of the 232Th decay series. A comparis
 on of the minimum detectable activity (MDA) values showed that the CSS gav
 e the lowest value for 228Ac\, 212Pb\, 212Bi and 208Tl while comparable va
 lues were obtained for other radionuclides.\n\nhttp://indico.cern.ch/contr
 ibutionDisplay.py?contribId=224&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=224&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Fluorescent Imaging of the Radiation Dose Surrounding an Iridium-1
 92 Seed Used in Brachytherapy
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-48@cern.ch
DESCRIPTION:Speakers: Dr. DENKOVA\, Antonia (TU Delft\, Netherlands)\nThe 
 energy transferred to the medium surrounding a small seed of a radioactive
  isotope decreases steeply with distance from the seed and depends on the 
 nature of the particulate and/or electromagnetic radiation emanating from 
 it. This highly-localized dose distribution is used to effect in brachythe
 rapy for the radiotherapeutic treatment of malignant tumours. Accurate mon
 itoring of such a steeply-varying dose distribution requires ideally a dos
 imetric technique capable of three-dimensional\, sub-millimetre spatial re
 solution. We have developed such a technique that is based on a gel medium
  that becomes fluorescent on exposure to ionizing radiation with the inten
 sity of the fluorescence proportional to the local radiation dose. We illu
 strate the method with photographic images of the fluorescence surrounding
  a high dose rate (HDR) seed of iridium-192. The images\, with a spatial r
 esolution of better than 0.1 mm\, were made in situ and could be recorded 
 in real time during the course of irradiation using time-lapse or video re
 cording modes. The gel is close to tissue-equivalent and its radio-fluorog
 enic property is based on the radiolytic formation of reactive free-radica
 ls. The measurements are therefore directly relevant to the radio-biologic
 al processes responsible for the destruction of malignant tissue. This met
 hod of real-time\, 3D dosimetry should expedite the research\, development
  and application of radio-nuclides for radiotherapy and provide a visual i
 mage that could be of use in the education and training of clinical person
 nel.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=48&sessionI
 d=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=48&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Characterisation of Radioactive Scales (NORM) Produced  by the Ons
 hore Oil and Gas Industry in the UK
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-49@cern.ch
DESCRIPTION:Speakers: Mr. AFOLABI\, Oluwasola (Radiochemistry Group\, Depa
 rtment of Chemistry\, Loughborough University\, LE11 3TU\, UK)\nThe occurr
 ence of radioactive scales in oil & gas production facilities is a major c
 oncern for the petroleum industry.  Activities exceeding 1KBq/g radium-226
  and 30KBq/g lead-210 have been reported in solid scales from the UK secto
 r. When progeny are taken into account\, total activities levels may excee
 d the UK threshold for Low Level Radioactive Waste (LLW) disposal. Increas
 ed radiation risks to operators and general public are now being addressed
  by revised legislation\; however the additional costs of waste management
  are yet to be fully assessed. Much of the work carried out to date has fo
 cussed on offshore NORM where the majority of arisings are disposed to sea
 . However\, onshore treatment\, where sea disposal is not an option\, pose
 s a serious challenge. \nThe aim of this project is to establish the natur
 e\, extent and distribution of NORM in UK onshore oil and gas fields and t
 o devise an effective NORM inhibition methodology for minimising future he
 alth\, environmental and economic impacts. Radiological surveys of product
 ion equipments are being undertaken and radiometric and isotopic analysis 
 are used to characterise radioactive scale deposits in representative UK o
 nshore oil & gas fields. Methods for inhibiting radium isotope co-precipit
 ation with common mineral phases such as barite and celestite\, are being 
 investigated by nucleating crystals in a counter diffusion system. Prelimi
 nary results are described.\n\nhttp://indico.cern.ch/contributionDisplay.p
 y?contribId=49&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=49&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Polymersomes as nano-carriers for alpha radion
 uclide therapy
DTSTART;VALUE=DATE-TIME:20120917T134000Z
DTEND;VALUE=DATE-TIME:20120917T135500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-46@cern.ch
DESCRIPTION:Speakers: Dr. DENKOVA\, Antonia (TU Delft\, Netherlands)\nAlph
 a radionuclide therapy has a great potential in the fight against cancer a
 s proven by a large number of pre-clinical and clinical studies [1\, 2]. I
 n vivo generators capable of delivering a highly efficient cascade of alph
 a particles are also steadily gaining importance. 225Ac is at the moment t
 he most important radionuclide that can serve as an in vivo generator\, pr
 oviding four alpha particles with a total energy of 28 MeV. However\, the 
 alpha emitting daughter nuclides of 225Ac may deviate from their intended 
 destination due to recoil and cause unwanted damage to healthy tissue. Her
 e\, we demonstrate that polymer vesicles (i.e. polymersomes)\, have great 
 potential to retain the recoiling daughter nuclides based on experimental 
 and simulation data. Experiments reveal that polymersomes with dimensions 
 of 100 nm can easily be loaded with radionuclides and are capable of retai
 ning more than 80 % of the daughter nuclide (209Pb) in the case of 213Po d
 ecay [3]. Doubling the size of the nano-carriers increases the retention t
 o 95 %. Furthermore\, simulation studies\, in which the whole decay chain 
 of 225Ac is considered\, indicate that polymersomes can be engineered in s
 uch a way that several consecutive recoiling daughters can be retained. Ac
 cording to these results double-layered polymersomes with dimensions of 80
 0 nm will enable the complete retention of the first daughter nuclide 221F
 r\, while the retention of the third radioactive daughter 213Bi will be in
 creased to 80 %. \n\n[1] Allen B.J.\, Raja C.\, Rizvi S.\, Li Y.\, Tsui W.
 \, Graham P.\, Thompson F.\, Reisfeld R.A.\, Kearsley J.\, Morgenstern A.\
 , Apostolidis C.\, Cancer Biol. Ther.\, 4\, 1318\, (2005).\n[2] Raja C.\, 
 Graham V.\, Abbas Rizvi S.M.\, Song E.\, Goldsmith H.\, Thompson J.\, Boss
 erhoff A.\, Morgenstern A.\, Apostolidis C.\, Kearsley J.\, Reisfeld R.A.\
 , Allen B.J.\, Cancer Biol. Ther.\, 6\, 846\, (2007).\n[3] Beuren J. van\,
  Wang G.\, Vries D. de\, Morgenstern A.\, Brucherseifer F.\, Wolterbeek H.
 T.\, Denkova A.G.\, submitted. \n[4] Thijssen L.\, Schaart D.R.\, de Vries
 D.\, A. Morgenstern A.\, Brucherseifer F.\, Denkova A.G.\, Radiochim. Acta
  2012 DOI: 10.1524/ract.2012.1935.\n\nhttp://indico.cern.ch/contributionDi
 splay.py?contribId=46&sessionId=17&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=46&sessionId=17
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Redox studies of the heaviest elements using an electrolytic colum
 n apparatus
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-86@cern.ch
DESCRIPTION:Speakers: Dr. TOYOSHIMA\, Atsushi (Japan Atomic Energy Agency\
 , Japan)\nRedox studies of the heaviest elements are fascinating because t
 hey provide information on the binding energies of the valence electrons w
 hich are expected to be influenced by increasingly strong relativistic eff
 ects. All heavy elements with atomic number ≥ 101 are produced in heavy-
 ion induced nuclear reactions. They are only available as short-lived radi
 oisotopes and only as single atoms. This means that standard electrochemic
 al techniques are not applicable to redox studies of the heaviest elements
 . Therefore\, we have developed a novel technique of electrolytic column c
 hromatography. While passing through one column\, single ions undergo elec
 trolytic oxidation or reduction and are chromatographically separated acco
 rding to their oxidation states. \nIn this paper\, we will present the ele
 ctrolytic reduction of trivalent mendelevium (Md\, element 101) and the ox
 idation of divalent nobelium (No\, element 102) using our newly developed 
 flow electrolytic column apparatus. All experiments were carried out at th
 e JAEA tandem accelerator in Tokai. Redox reactions of Md and No\, between
  the 2+ and 3+ states\, were clearly observed. Redox potentials of these e
 lements were successfully determined based on observed amounts of the oxid
 ized or reduced state as a function of the applied potential. \nIn the pre
 paration of future experiment with seaborgium (Sg\, element 106)\, we rece
 ntly began a study on the reduction of the lighter group-6 homologs Mo and
  W using an electrolytic column apparatus. Our recent results of the reduc
 tion of Mo and W will be also presented.\n\nhttp://indico.cern.ch/contribu
 tionDisplay.py?contribId=86&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=86&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Comparison of  Quantitative Neutron Capture Ra
 diography\, Inductively Coupled Plasma Mass Spectrometry\, and  Prompt Gam
 ma Activation Analysis for Boron Determination in Biological Samples
DTSTART;VALUE=DATE-TIME:20120920T084000Z
DTEND;VALUE=DATE-TIME:20120920T085500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-44@cern.ch
DESCRIPTION:Speakers: Dr. SCHÜTZ\, Christian (Institute for Nuclear Chemi
 stry\, University of Mainz\, Fritz-Strassmann-Weg 2\, D-55099 Mainz\, Germ
 any)\nCategory: Radioanalytical Chemistry and Nuclear Analytical Technique
 s\nType of presentation: Oral presentation\n\nComparison of  Quantitative 
 Neutron Capture Radiography\, Inductively Coupled Plasma Mass Spectrometry
 \, and \nPrompt Gamma Activation Analysis for Boron Determination in Biolo
 gical Samples\n\nC. L. Schütz\, C. Brochhausen\, D. Iffland\, J.V. Kratz\
 , B. Kuczewski\,\nG. Otto\, T. Schmitz\, G. Hampel\n\n\nIntroduction:\nBor
 on determination is most commonly carried out in water and geological samp
 les. Its determination in blood and tissue samples is a crucial task espec
 ially for treatment planning\, preclinical research\, and clinical applica
 tion of BNCT. However\, comparison of clinical findings remains difficult 
 due to a variety of analytical methods\, protocols and standard reference 
 materials in use [1]. This abstract addresses the comparability of Inducti
 vely Coupled Plasma Mass Spectrometry (ICP-MS)\, Quantitative Neutron Capt
 ure Radiography (QNCR)\, and Prompt Gamma Activation Analysis (PGAA) for t
 he determination of boron in biological samples\, using blood and tissue s
 amples from a clinical study for the comparison. The methodical comparison
  of ICP-MS\, ICP-OES\, PGAA\, and QNCR is of general interest\, because th
 ese are the most frequently used methods for quantitative analysis in clin
 ically relevant studies\n\n\nMaterials and Methods:\nBlood and tissue samp
 les were obtained from a clinical study to investigate the uptake behaviou
 r of p-boronophenylalanine-fructose (BPA-f) in cancerous and tumour free l
 iver tissue. Since the boron distribution within a sample taken from tumou
 r free liver tissue was very homogeneous\, it serves as an ideal sample ma
 trix to compare methods for integral and locally selective boron analyses.
  To be able to compare data from ICP-MS or PGAA directly to those obtained
  by QNCR\, a set of reference blood samples was included in the comparison
 \, which before had been used for the production of reference standards fo
 r analysis by QNCR [2]. Irradiations for QNCR and PGAA took place at the r
 esearch reactors of the University of Mainz\, the HFR Petten\, the Netherl
 ands\, and the FRM II of the Technical University of Munich\, Germany.\nTh
 e larger part of the tissue biopsies could be analysed by all three method
 s\, thus creating a situation similar to a Round-Robin trial. The blood sa
 mples were first analysed by PGAA and then by ICP-MS\, since the latter re
 quired wet-ashing for sample preparation. The measurements by QNCR and PGA
 A\, as well as the related clinical study are described in detail elsewher
 e [2\, 3]. \nResults and discussion:\nConsistency and conformity of ICP-MS
  and PGAA measurements for blood samples in a range of 0 – 30 ppm 10B wa
 s very good. From previous works\, it is known that both methods relying o
 n the inductively coupled plasma showed little difference in performance w
 hen measuring samples equally prepared following the same protocol [4\, 5]
 . Also\, comparison of ICP-OES to PGAA had revealed good agreement [6]. \n
 However\, for none of the three methods accordance with QNCR has been foun
 d so far. In previous works\, Probst et al. concluded that differences to 
 QNCR may be due to the fact that ICP-MS and ICP OES could not account for 
 the very heterogeneous boron concentration that can occur in tissue sample
 s. In this respect\, tumour free liver tissue appears as a very suitable 
 “model system” to overcome this problem\, which could be demonstrated 
 by very consistent measurements comparing the three methods included in th
 e comparison.\n\n\nConclusion:\nThe data of all methods and their comparis
 on revealed that it is possible to obtain matching results from all three 
 methods for a specific type of organic sample (tumour free liver tissue). 
 also demonstrating the possibility to obtain consistent results from analy
 tical techniques for integral boron determination in comparison to a local
 ly selective method. \nReference materials in use for analytical\, and esp
 ecially radioanalytical\, boron determination by groups worldwide vary in 
 their characteristics depending on each method. For standardisation of ana
 lytical protocols\, BPA-f in whole blood is suitable for comparison of ICP
 -MS\, ICP-OES\, PGAA and\, indirectly\, for QNCR and could therefore serve
  in a larger Round-Robin trial as reference material. \n\n\nReferences\n\n
 1.	Probst TU (1999) Fresenius' Journal of Analytical Chemistry 364(5):391
 –403\n2.	Schütz C et al. (2011) Radiation Research 176:388–396\n3.	Sc
 hmitz T et al. (2011) Applied Radiation and Isotopes 69(7):936–941\n4.	N
 yomora AMS et al. (1997) Fresenius' Journal of Analytical Chemistry 357(8)
 :1185–1191\n5.	Laakso J et al. (2001) Clin Chem 47(10):1796–1803\n6.	R
 aaijmakers CPJ et al. (1995) Acta Oncologica 34(4):517–523\n\nhttp://ind
 ico.cern.ch/contributionDisplay.py?contribId=44&sessionId=27&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=44&sessionId=27
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Nanomedicine Approaches of Radioactive Gold Na
 noparticles In Cancer Therapy
DTSTART;VALUE=DATE-TIME:20120919T152000Z
DTEND;VALUE=DATE-TIME:20120919T153500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-42@cern.ch
DESCRIPTION:Speakers: Prof. KATTI\, Kattesh (University of Missouri\, USA)
 \nThe most practiced approach of drug delivery in cancer therapy over the 
 last century has involved intravenous administration of cytotoxic chemothe
 rapeutic or radionuclide-based nuclear medicine agents. Limited affinity o
 f targeted chemotherapeutic agents or radiopharmaceuticals to tumor cites 
 and also the vascular and interstitial transport barriers continue to pose
  vexing challenges in achieving optimal therapeutic payloads at tumor site
 s. Therefore\, effective therapy of solid tumors continues to be an unmet 
 clinical need. Gold nanoparticles\, because of their size\, inherent thera
 peutic properties and targeting capabilities provide unprecedented opportu
 nities for intratumoral delivery and are thus poised for major advances in
  cancer oncology. Nanoparticles derived from 198Au ( a radioisotope of gol
 d produced in nuclear reactors) are inherently therapeutic possessing idea
 l beta energy emission and half-life for effective destruction of tumor ce
 lls/tissue (βmax = 0.96 MeV\; half-life of 2.7 days). We hypothesized tha
 t the intratumoral delivery of naturally available\, non-toxic and FDA app
 roved Gum Arabic functionalized radioactive gold nanoparticles (GA-AuNPs) 
 will circumvent vascular and interstitial transport barriers resulting in 
 targeted delivery of optimal therapeutic payloads with minimal/no toxicity
  to neighboring tissue. Detailed therapeutic efficacy studies in prostate 
 tumor bearing SCID mice\, injected with GA -198AuNP intratumorally\, have 
 demonstrated excellent retention of therapeutic payload (90%) and an overa
 ll tumor volume reduction of over 80% through a single intra tumor injecti
 on of GA-198AuNPs(1).  These therapeutic efficay data provide compelling i
 mpetus for the clinical translation of this novel nanotherapeutic agent fo
 r treating a variety of solid tumors which include prostate\, pancreatic a
 nd hepatic tumors in human patients.  This presentation will present lates
 t results on the utility of radioactive gold nanoparticles in prostate tum
 or therapy. This lecture will focus on presenting the realistic potential 
 of GA-198AuNPs in the effective treatment of hormone refractory prostate a
 nd other solid tumors which normally manifest resistance in response to tr
 aditional cell killing therapies. New oncological approaches toward extend
 ing survival of prostate cancer patients as the GA-198AuNPs transform tumo
 rs from fast propagating to static stages will also be discussed.\n\n(1). 
 Kannan and Katti et. al:. Functionalized Radioactive Gold Nanoparticles in
  Tumor Therapy. Wiley Interdisciplinary Reviews: Nanomedicine and Nanobiot
 echnology\, Volume 4 Issue 1 (January/February 2012)\; Article first publi
 shed online: 22 SEP 2011\; DOI: 10.1002/wnan.161\n\nhttp://indico.cern.ch/
 contributionDisplay.py?contribId=42&sessionId=25&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=42&sessionId=25
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Sequential separation of ultra-trace U\, Th\, Pb\, and lanthanides
  with a single anion-exchange column
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-43@cern.ch
DESCRIPTION:Speakers: Dr. MIYAMOTO\, Yutaka (JAEA\, Japan Atomic Energy Ag
 ency\, Japan)\nAbundance and isotopic ratios of trace uranium (U)\, thoriu
 m (Th)\, lead (Pb) and lanthanides in environmental samples play a key rol
 e to investigate features of the samples. In the environmental samples suc
 h as rocks\, soils\, and airborne dusts\, trace U\, Th\, Pb\, and lanthani
 des are contained with major elements such as Na\, K and Fe. These major e
 lements and the polyatomic ions which originated from the co-existing elem
 ents affect accuracy of analytical results measured by ICP-MS. The analyte
 s\, therefore\, should be separated from the interfering elements. The aut
 hors developed the technique for sequential separation of U\, Th\, Pb\, an
 d the lanthanides using a single anion-exchange column and mixed media con
 sisting of hydrochloric acid\, nitric acid\, acetic acid\, and hydrofluori
 c acid. With a single anion-exchange column\, sequential separation of 50 
 ng each of the elements of interest in an ICP-MS calibration solution was 
 successfully carried out. The recovery yields of these elements were more 
 than 95%. Alkali metals\, alkali earth metals\, and Fe were eliminated fro
 m these elements. This sequential separation technique was applied to the 
 author's own simple automatic system. The system consists of a tiny anion-
 exchange column\, switching valves controlled by a PC\, and a gas bottle t
 o pressurize the eluents. The separation of elements of interest was optim
 ized for several parameters including particle size\, column length\, and 
 flow rate of eluents. The elements of interest were completely separated w
 ithin 6 hours by use of this system.\n\nhttp://indico.cern.ch/contribution
 Display.py?contribId=43&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=43&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Development of Decontamination Method Using Io
 nic Liquid as a Medium for Treating Waste Contaminated with Uranium
DTSTART;VALUE=DATE-TIME:20120918T162500Z
DTEND;VALUE=DATE-TIME:20120918T164000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-40@cern.ch
DESCRIPTION:Speakers: Mr. OHASHI\, Yusuke (Ningyo-toge Environmental Engin
 eering Center\, Japan Atomic Energy Agency\, Japan)\nMost of the metal or 
 bed material wastes generated from uranium enrichment facilities or uraniu
 m refining and conversion plants are contaminated by uranium fluoride comp
 ounds. It is desirable to recover as much uranium as possible from these w
 astes. Additionally\, if these wastes are decontaminated up to a level reg
 arded as nonradioactive waste\, the decontaminated materials should be reu
 sed. \n\nIn this study\, we have evaluated the feasibility of application 
 of 1-butyl-3-methyl-imidazolium chloride (BMICl) and cholin chloride-urea 
 (CCU) ionic liquids to the treatments of metal waste contaminated with ura
 nium. \nDissolution experiments were carried out by adding UF4 powder samp
 les into BMICl and CCU under atmospheric conditions. UF4 samples were comp
 letely dissolved in BMICl after around 6h at 100 ºC\, and 38% of samples 
 were also dissolved in CCU after 5 h at 100 ºC. Steel waste contaminated 
 with UF4 was also decontaminated using BMICl at 100 ºC under atmospheric 
 conditions. The uranium concentrations of metal waste were found to decrea
 se below the clearance level (1Bq/g) within 3h. \n\nCyclic voltammograms o
 f the sample solutions prepared by dissolving steel waste into BMICl were 
 measured. The reversible and irreversible peaks were observed around 0 and
  -1.2 V\, respectively. These peaks were assigned as one electron reductio
 n process of Fe3 + and one electron reduction process of UO22+\, respectiv
 ely. These results suggest that electrolytic deposition of uranium should 
 be performed without mixing of iron deposit. Bulk electrolysis of sample s
 olutions prepared by dissolving steel waste into BMICl was also carried ou
 t at -1.5V at 80 ºC. The deposits were formed on a carbon electrode as ca
 thode. In analyses of deposits using XPS\, only uranium component was dete
 cted. \n\nConsequently\, we confirmed that BMICl and CCU are effective med
 ia for the decontamination of uranium waste and that uranium can be recove
 red selectively from BMICl solution containing iron by the electrolytic me
 thod.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=40&session
 Id=22&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=40&sessionId=22
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Validation of neutron induced data up to 18 MeV for production of 
 the therapeutic radionuclide 67Cu
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-118@cern.ch
DESCRIPTION:Speakers: Dr. HUSSAIN\, Mazhar (Government College University\
 , Lahore\, Pakistan)\nThe radionuclide 67Cu can be produced via several ro
 utes. Initially the 67Zn(n\,p)67Cu reaction was applied using a nuclear re
 actor. In a recent CRP of IAEA\, the study of production of this radionucl
 ide is in progress via the 67Zn(n\,p)67Cu\, 68Zn(p\,2p)67Cu and 70Zn(p\,α
 )67Cu reaction. In this work we have validated the neutron induced data fo
 r the production of 67Cu. The validation is based on integral test of the 
 recommended data that were deduced from calculations done by using nuclear
  model codes STAPRE\, EMPIRE\, TALYS and ALICE-IPPE as well as by the stat
 istical approach of fitting the experimental data.\nKeywords: Radionuclide
 s\, Nuclear model calculations\, Validation\, Integral tests.\n\nhttp://in
 dico.cern.ch/contributionDisplay.py?contribId=118&sessionId=26&confId=1834
 05
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=118&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Nuclear and radioanalytical techniques in nanotoxicology research:
  studies on the Rabbit Reproductive System
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-1@cern.ch
DESCRIPTION:Speakers: Prof. GROPPI\, Flavia (LASA\, Università degli Stud
 i di Milano and INFN-Milano\, Italy)\nNanotechnology\, perceived as one of
  the key technologies of this century. Despite the term "nanotechnology" i
 s synonymous with things that are innovative and highly promising\, little
  attention has been dedicated to the other side of the coin\, i.e. the res
 earch on toxicological effects and on the relations with factors that can 
 affect the nanotoxicity on human health and on the environment. Research o
 n the impact of engineered nanoparticles (NPs) is strongly hampered by a l
 ack of reliable tools to detect\, visualize and quantitatively trace parti
 cles movement and transfer in complex environmental and biological systems
 . A few methods\, such as labelling with fluorescent probes\, may overcome
  some of the detection problems\; however\, leading a significant modifica
 tion of the particles to be traced\, the engineered NPs behavior is modifi
 ed. Conversely radiolabelling or radioactivate the NPs to make them distin
 ctive and thus easily detectable\, is one very smart way to solve the prob
 lem especially because after neutron or proton activation the physicochemi
 cal characteristics in terms of size distribution and Z potential are main
 tained as the “cold” ones. One of the debated themes is the influence 
 of NPs on the human reproductive system. In this contest a way to have exp
 erimental evidence is the study of AuNPs and AgNPs passage through the blo
 od-testicular barrier in vivo. In this work some preliminary results obtai
 ned by NAA of the sperma (seminal liquid plus sperms) from selected strain
  of rabbits are presented. Samples were taken from animals exposed for dif
 ferent time (3 and 7 days) to 5 mg AgNPs and AuNPs kg-1 b.w.\n\nhttp://ind
 ico.cern.ch/contributionDisplay.py?contribId=1&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=1&sessionId=26&
 confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - Nuclear and radioanalytical techniques in nanoto
 xicology research
DTSTART;VALUE=DATE-TIME:20120919T125000Z
DTEND;VALUE=DATE-TIME:20120919T131000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-78@cern.ch
DESCRIPTION:Speakers: Dr. SABBIONI\, Enrico (European Center for the Susta
 inable Impact of Nanotechnology-ECSIN\, Veneto Nanotech ScpA\, Italy)\nCur
 rently\, enormous progress is being made in producing a great number of na
 nomaterials. However\, in spite of hundreds of nano-products produced and 
 currently available on the market a huge health and safety questions remai
 n unsolved\, and the assessment of possible health risks of nanoscale mate
 rials before they become ubiquitous in every aspects of life is necessary.
  In order to reach this goal nanotoxicology research has become a new fron
 tier for a scientifically-based assessment of the environmental and human 
 health impact of nanomaterials and nanoparticles (NP). In this context\, t
 here are a large number of challenges for the analytical chemist involved 
 in the different steps of nanotoxicology research such as the physico-chem
 ical characterization of NP and their use in in vivo and in vitro experime
 nts with laboratory animals and cellular moedels (behaviour in biological 
 media\, toxicokinetics\, uptake in whole tissue/ cells\, intracellular dis
 tribution\, binding with biomolecules). However\, nanotoxicology research 
 has a strong multidisciplinary character and requires an integrated use of
  different analytical techniques such as spectrochemical\, nuclear and rad
 iochemical\, specialized microscopy\, bioanalytical\, and molecular biolog
 y techniques.\nThe aim of this work is to highlight the potential role tha
 t nuclear and radiochemical techniques plays in mechanistically-based nano
 (eco)toxicology research carried out at ECSIN in collaboration with the ra
 diochemical laboratory of the University of Milan-INFN Section.\nApplicati
 ons carried out are based on the use of radioactive metallic zerovalent or
  metal oxide NP (198AuNPs\, 110mAgNPs\, 60CoNPs\, 59FeNP\, 58NiNPs and 57C
 o59Fe2O4) as radiolabelled by neutron irradiation or via radiochemical syn
 thesis by no-carrier-added (NCA) radiotracers.\nThe need of a new speciali
 zed figure of radiochemist\, the radionanoanalytical chemist\, will be als
 o stressed.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=78&s
 essionId=25&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=78&sessionId=25
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Local Fields at Nonmagnetic Probe Sites in a P
 erovskite La0.7Ca0.3MnO3
DTSTART;VALUE=DATE-TIME:20120918T111000Z
DTEND;VALUE=DATE-TIME:20120918T112500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-201@cern.ch
DESCRIPTION:Speakers: Dr. SATO\, Wataru (Institute of Science and Engineer
 ing\, Kanazawa University\, Japan)\nPerovskite manganese oxides (AMnO3) ar
 e known to exhibit the effect of colossal magnetoresistance (CMR)\, a phen
 omenon that electrical resistivity undergoes a drastic change as large as 
 five to six orders of magnitude by an applied magnetic field.  Because of 
 this unique physical property\, much attention has been given to these oxi
 des aiming at wide industrial applications.  In order to realize practical
  use of these compounds\, it is of importance to obtain information on loc
 al fields in the material as well as macroscopic quantities such as resist
 ivity and magnetization.\nFrom this point of view\, we have applied the ti
 me-differential perturbed angular correlation (TDPAC) method to a study of
  a perovskite La0.7Ca0.3MnO3\, which exhibits the CMR effect by the parama
 gnetic-ferromagnetic phase transition (Tc ~ 245 K).  In our previous work\
 , we successfully observed drastic change in the local field at the probe 
 nucleus\, 140Ce\, between temperatures above and below Tc\, which evidentl
 y suggests that the magnetic field produced by spins in Mn ions can be tra
 nsferred to the probe at the A site.  Since the 140Ce probe arising from t
 he disintegration of 140La takes two possible oxidation states\, 140Ce3+ a
 nd 140Ce4+\, however\, it remains unknown whether the observed magnetic fi
 eld (= 6.9 (3) T at 240 K) is exclusively transferred from Mn spins or is 
 produced in part by a 4f electron spin localized at the probe in the chemi
 cal state of 140Ce3+.  In the present work\, therefore\, we employed nonma
 gnetic 111Cd(←111mCd) and 111Cd(←111In) as the probe nuclei to shed li
 ght on the local field without self-owned spins.  In the session\, the eff
 ect of the 4f electron is discussed.\n\nhttp://indico.cern.ch/contribution
 Display.py?contribId=201&sessionId=21&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=201&sessionId=2
 1&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Extraction behavior of Mo(VI)\, Mo(V)\, W(VI)\, and W(V) from HCl 
 solutions by Aliquat 336
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-200@cern.ch
DESCRIPTION:Speakers: Mr. YOKOKITA\, Takuya (Graduate School of Science\, 
 Osaka University\, Japan)\nIt is expected that the element 106 seaborgium 
 (Sg) is redox active\, because molybdenum (Mo) and tungsten (W)\, the homo
 logues of Sg\, have various oxidation states. Electrochemistry of superhea
 vy elements (SHEs)\, including Sg\, with atomic numbers ≥ 104 is very in
 teresting\, because valence electron structure of SHE would be influenced 
 by strong relativistic effect. However\, the voltammetry for measurement o
 f redox potential cannot be applied to SHE chemistry\, because the SHE nuc
 lides can only be produced as one atom at a time and have short half-lives
 . Therefore\, the investigation of reduction potential of Sg ion should be
  combined with chemical separation to obtain reduction ratio of Sg. We are
  planning to study the reduction behavior of Sg by the electrochemical met
 hod combined with solvent extraction.\nWe carried out solvent extraction o
 f Mo(VI)\, Mo(V)\, W(VI)\, and W(V) in 0.01–0.36 M Aliquat 336 / 0.1–1
 1 M HCl system as model experiments for Sg. The HCl solutions of Na2[MoO4]
 •2H2O\, [MoCl5]\, and Na2[WO4]•2H2O were used for extraction of Mo(VI)
 \, Mo(V)\, and W(VI)\, respectively. The HCl solutions for Mo(V) and W(V) 
 were prepared by electrochemical method and SnCl2•2H2O as reductant\, re
 spectively. Extraction behaviors of mononuclear Mo and W were investigated
  using carrier-free radiotracers 99Mo and 181W\, which were produced as 23
 5U(n\, f) and 181Ta (p\, n) reaction\, respectively. \nThe distribution ra
 tios (D) of Mo(V) and W(V) were higher than those of Mo(VI) and W(VI)\, re
 spectively. The D values for Mo(V) obtained by the reduction of Mo(VI) wer
 e in good agreement with those obtained with [MoCl5]\, suggesting that red
 uction behavior of the group-6 elements can be observed by solvent extract
 ion. The D values of carrier-free Mo(VI) and W(VI) are almost the same as 
 those with macro amounts in 6–11 M HCl. This condition would be suitable
  for the Sg experiments.\n\nhttp://indico.cern.ch/contributionDisplay.py?c
 ontribId=200&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=200&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Distribution and transfer of radionuclides inclu
 ding iodine-131 in Japanese environment following the Fukushima nuclear ac
 cident
DTSTART;VALUE=DATE-TIME:20120921T092000Z
DTEND;VALUE=DATE-TIME:20120921T094000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-203@cern.ch
DESCRIPTION:Speakers: Prof. MURAMATSU\, Yasuyuki (Gakushuin University\, J
 apan)\nA large amount of radionuclides was released from the accident of F
 ukushima Daiichi Nuclear Power Plant in March 2011. We have studied distri
 bution of radiocaesium and radioiodine in the environment and their transf
 er to agricultural products. Shortly after the accident\, high iodine-131 
 concentrations were observed in leaf vegetables harvested in Fukushima and
  surrounding Prefectures. The levels of iodine-131 in vegetables decreased
  markedly in April due to the termination of the release and to its short 
 half-life (8 days)\, then attention has been paid to radiocaesium (caesium
 -134 and caesium-137) deposited in soil. Results of the monitoring for agr
 icultural crops harvested during spring to autumn showed that no higher va
 lues of radiocaesium were found in most vegetables cultivated in Fukushima
  Prefecture\, excluding the evacuation area. However\, values higher than 
 the provisional guideline for radiocaesium (500 Bq/kg) were found in some 
 agricultural products such as bamboo shoots\, some fruits (e.g. Japanese c
 itron\, persimmon) and new tea leaves. These facts could not be explained 
 by root-uptake pathway. Translocation pathway from leaves and barks should
  be important to understand the contamination of the other organs in the p
 lants. Higher radiocaesium concentrations (>500 Bq/kg) were observed in so
 me areas\, although the most of rice in the same area showed the values ma
 rkedly lower than 100 Bq/kg. We have studied possible mechanisms for the e
 nhancement of radiocaesium in crops.\n   Since there are not enough data o
 f iodine-131 to understand its detailed spatial distribution\, we have ana
 lyzed iodine-129 by AMS to examine whether there is any relationship betwe
 en these two isotopes in soil. It is interesting to note that a relatively
  good correlation was found between the concentrations of iodine-131 and i
 odine-129. This finding suggests the usefulness of iodine-129 analysis for
  the retrospective evaluation of iodine-131 depositions following the acci
 dent.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=203&sessio
 nId=31&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=203&sessionId=3
 1&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - The very powerful UCN source at the reactor TRIG
 A Mainz - Application for precise measurements of the neutron half-life
DTSTART;VALUE=DATE-TIME:20120918T155000Z
DTEND;VALUE=DATE-TIME:20120918T161000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-145@cern.ch
DESCRIPTION:Speakers: Dr. SOBOLEV\, Yury (Johannes-Gutenberg Universität 
 Mainz\, Institut für Kernchemie\, Germany)\nUltracold neutrons (UCN) are 
 free neutrons with very low kinetic energies corresponding to v~ 5m/s. The
 y can be stored both in material and magnetic traps and thus observed hund
 reds of seconds limited only by their natural lifetime. The long observati
 on times make it possible to perform precision experiments on the neutron'
 s  fundamental properties such as the search for its electric dipole momen
 t. Recently a new powerful UCN source has been installed at the pulsable r
 eactor TRIGA Mainz. This source is well adapted to perform storage type ex
 periments even at small research reactors. We plan to use the UCN source f
 or precision experiments of the neutron half-life using magnetic storage m
 ethods. A status report on the UCN source and its application will be pres
 ented.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=145&sessi
 onId=22&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=145&sessionId=2
 2&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Polonium Evaporation Studies from Liquid Lead-based Alloys
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-142@cern.ch
DESCRIPTION:Speakers: Mr. RIZZI\, Matthias (Paul Scherrer Institut\, Switz
 erland)\nLiquid lead and liquid lead-based alloys are currently in discuss
 ion for application as spallation target material and coolant in neutron s
 ources and Accelerator Driven Systems (ADS). The main disadvantage of lead
 -based alloys is the formation of Po-210 by nuclear reactions. This radion
 uclide is an alpha-emitter with a half-life of 138.8 days and therefore of
  high radiological concern due to inhalation or ingestion in case of its r
 elease to the environment. The production of this polonium isotope is espe
 cially pronounced in bismuth containing alloys such as lead bismuth eutect
 ic (LBE)\, which is foreseen as spallation target material and reactor coo
 lant in the ADS prototype MYRRHA. To reduce the hazard resulting from polo
 nium release\, pure lead and lead gold eutectic (LGE) are considered as al
 ternative liquid spallation target materials and reactor coolants. Though 
 the production of polonium in these materials is much lower compared to LB
 E\, still considerable amounts are formed. Therefore it is crucial for the
  licensing of such facilities to study the release behavior of polonium fr
 om these materials. In the present study we have investigated the evaporat
 ion behavior of Polonium from pure lead and lead-gold eutectic using the t
 ranspiration technique. The results are compared with earlier measurements
  of polonium evaporation from LBE.\n\nhttp://indico.cern.ch/contributionDi
 splay.py?contribId=142&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=142&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Advanced Fuels for Generation IV reactors: Reprocessing and Dissol
 ution – ASGARD
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-143@cern.ch
DESCRIPTION:Speakers: Dr. RETEGAN\, Teodora (Chalmers University of Techno
 logy\, Sweden)\n*The above authors are: the Coordinator of the project and
  the Domain Leaders. However\, the project is a much larger effort with up
  to 90 contributors.\n\nASGARD is a Large Scale Integrated Project having 
 as main objective the research on advanced/novel nuclear fuel fabrication 
 and their respective reprocessing issues for Generation IV reactors. \nThe
  Strategic Energy Technology plan (SET-plan) of the European Commission id
 entifies fission energy as an important contributor to meet long-term obje
 ctives for reduction of greenhouse gas emissions. Sustainability of nuclea
 r power may be achieved by the introduction of fast neutron Generation IV 
 reactors and their associated fuel cycle facilities\, as described in the 
 Strategic Research Agenda (SRA) of the Sustainable Nuclear Energy Technolo
 gy Platform (SNE-TP).\nThe project seeks integration between reactor\, fue
 l and recycling communities\, which today is lacking. In some cases it res
 ults in discrepancies between the reactor design on one hand\, and the tec
 hnological feasibility of fabricating\, dissolving and reprocessing the se
 lected fuel on the other hand. \nOxide\, Nitride and Carbide type of nucle
 ar fuels are addressed with focus on dissolution\, reprocessing and fabric
 ation behavior. \nIt is an integrated effort of 16 institutions from 9 cou
 ntries\, and additional: Scientific Advisory Commission (4 representatives
 ) and an Industrial Users Group (5 representatives). \nThe consortium cons
 ists on partners who have an extensive experience in research on fabricati
 on of various kinds of fuels and in the recycling process.  In addition\, 
 basic science laboratories participate with large capabilities in handling
  of highly active radioactive materials such as Chalmers University of Tec
 hnology\, Sweden as well as national research laboratories and also univer
 sity laboratories with more limited radiochemical possibilities.\nIn order
  to ensure the know-how and appropriate training of the future generation\
 , the project will allocate a large space to training and dissemination. T
 raining sessions will consist on well selected lectures and hands-on train
 ing as well as summer schools. A travel fund is allocated for mobility of 
 students and teachers and will be based on travel grant system with define
 d rules. \nThe main goal is to ensure the sustainability and safety of fut
 ure nuclear power fleet.\nIt is funded by the 7th Framework Program (FP7) 
 of the European Commission (Euratom). \nIt was officially launched on the 
 11th of January\, 2012 and will continue for four years.\n\nhttp://indico.
 cern.ch/contributionDisplay.py?contribId=143&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=143&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Gallium-68 complexes of NOTA-bis(phosphonates) conjugates as radio
 tracers for bone imaging with PET
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-140@cern.ch
DESCRIPTION:Speakers: Mr. HOLUB\, Jan (Charles University in Prague\, Facu
 lty of Science\, Department of Inorganic Chemistry\, Czech Republic)\nThis
  work reports on synthesis\, complexation and radiolabeling study of new m
 acrocyclic ligands for selective complexation of gallium\, which might ser
 ve as potential radiopharmaceuticals for 68Ga-PET bone imaging. Bone-targe
 ting bis(phosphonic) acid moiety\, as a distant\, non-coordinating group w
 as appended to the 1\,4\,7-triazacyclonone-1\,4-diacetic acid macrocyclic 
 fragment through acetamide or methylphosphinic spacer. Complexation of Ga(
 III) was studied under different temperature and pH levels by means of 71G
 a\, 31P and 1H NMR spectroscopy. Complex formation proceeds through interm
 ediate steps involving bis(phosphonate) coordination. Hydrolysis of amide 
 bond of the carboxoamidebis(phosphonate) was also observed during the comp
 lexation reaction\, leading to the Ga(III)-NOTA complex\, confirmed by X-r
 ay diffraction. Under all tested conditions\, ligand with methylphosphinat
 e linker showed faster complexation rate than the acetamide. Results from 
 NMR studies (milimolar concentrations) were comparable with gallium-68 rad
 iolabeling study (picomolar concentrations). In vitro sorption study showe
 d effective binding of the complexes to hydroxyapatite\, which was used as
  a model of real bone tissue. Selective bone uptake was confirmed by in vi
 vo PET imaging on laboratory rats.\n\nhttp://indico.cern.ch/contributionDi
 splay.py?contribId=140&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=140&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - CINCH - Cooperation in education In Nuclear Chem
 istry
DTSTART;VALUE=DATE-TIME:20120920T120000Z
DTEND;VALUE=DATE-TIME:20120920T122000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-141@cern.ch
DESCRIPTION:Speakers: Prof. JOHN\, Jan (Czech Technical University in Prag
 ue\, Brehova 7\, 115 19 Prague\, Czech Republic)\nThe renaissance of nucle
 ar power is already requiring a significant increase in the number of the 
 respective specialists\, amongst others are nuclear chemists. The project 
 Cooperation In education in Nuclear CHemistry (CINCH) aims to coordinate t
 he current fragmented and diverse activities in Nuclear Chemistry educatio
 n and training in Europe both at Ph.D. and undergraduate levels\, in colla
 boration with Russia. The system developed should enable formation of a lo
 ng-term Euratom Fission Training Scheme (EFTS) and contribute to moving th
 e education and training in nuclear chemistry to a qualitatively new level
 . The work has been coordinated also with activities of ENEN association\,
  Division of Nuclear and Radiochemistry of EuChemMS\, and the training mod
 ules of EUROATOM “chemical” IPs and NOEs.\n\nThe main results of the p
 roject with the broadest impact to students\, teachers\, industries\, and 
 research community will be a set of compact joint modular courses in diffe
 rent branches of modern nuclear chemistry\, an e-learning platform availab
 le for both education and training (both applicable at the Ph.D.\, life-lo
 ng learning\, and MSc. levels)\, and a long term sustainable strategy for 
 nuclear chemistry education. In this presentation\, examples of the struct
 ures of the courses developed will be given and other project activities w
 ill be reviewed.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId
 =141&sessionId=29&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=141&sessionId=2
 9&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Airborne radionuclides measured in Wako\, Japan\, after the Fukush
 ima Dai-ichi nuclear power plant accident in 2011
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-209@cern.ch
DESCRIPTION:Speakers: Mr. KANAYA\, Jumpei (RIKEN\, Japan)\nOn March 11\, 2
 011\, an earthquake of magnitude 9.0 occurred near the east coast of Honsh
 u\, Japan\, and was followed by a large tsunami. The disasters caused dama
 ge to the Fukushima Dai-ichi nuclear power plant (FDNPP)\, resulting in th
 e release of radionuclides into the environment. Hence\, we initiated an u
 rgent measurement of the radioactivity concentrations of airborne radionuc
 lides at the RIKEN Wako Institute (35°46'44'' N\, 139°36'54'' E)\, Wako\
 , Japan\, located about 220 km to the southwest of FDNPP.\nAir dust was co
 llected using a commercially available air dust sampler (M&F Enterprise SP
 -30). Dust was collected for 30 min for the first two samples F01 and F02 
 in the period March 15 11:15–11:45 (Japan Standard Time\, JST) and March
  16 13:15–13:45\, respectively. After the third sample from March 16 18:
 32 to March 17 9:00\, dust was continuously collected for about one year u
 sing a total of 84 filters (F03–F86). The filter samples were subjected 
 to γ-ray spectrometry using a Ge detector.\nIn this work\, radioactivity 
 concentrations were determined for Ba-140\, Cs-137\, Cs-136g\, Cs-134g\, I
 -133g\, Te-132\, I-131\, Te-129m\, Ag-110m\, Mo-99\, and Nb-95g. The highe
 st radioactivity concentrations for typical radionuclides in unit Bq/m^3 w
 ere 8.8 ± 0.2 for Cs-137\, 1.2 ± 0.2 for Cs-136g\, 8.5 ± 0.2 for Cs-134
 g\, 4.7 ± 0.3 for I-133g\, 58 ± 2 for Te-132\, 8.0 ± 1.2 for Te-129m\, 
 and 35 ± 1 for I-131 in the F01 sample The time variations of the radioac
 tivity concentrations and their ratios in Wako are discussed by referring 
 to those of the ambient effective dose rate as well as the amount of rainf
 all\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=209&sessionI
 d=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=209&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Radiochemical and cross section studies for the production of the 
 therapeutic radionuclide <sup>193m</sup>Pt
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-208@cern.ch
DESCRIPTION:Speakers: Dr. SCHOLTEN\, Bernhard (Forschungszentrum Juelich G
 mbH\, Germany)\nThe radionuclide 193mPt (T1/2 = 4.33 d) decays by highly c
 onverted isomeric transition emitting about 33 Auger electrons. It is of g
 reat potential interest in internal radiotherapy because of its suitable d
 ecay properties. So far the specific activity of 193mPt produced has been 
 rather low due to the use of the 192Pt(n\,γ)-process at a reactor. The ai
 m of this work was to measure the excitation function of the 192Os(α\,3n)
  reaction. Furthermore\, the yield and the specific activity of 193mPt pro
 duced was determined. \n    The dissolution of osmium\, its conversion to 
 OsO4 vapor and trapping in KOH solution for electrolytic preparation of th
 in target samples of highly enriched 192Os on Ni as well as the complete r
 adiochemical separation of radioplatinum including 192Os recovery were opt
 imized.\n    The excitation function of the 192Os(α\,3n) 193mPt reaction 
 was measured up to 39 MeV using the stacked-foil activation technique with
  99.65 % enriched 192Os targets at the Brussels Cyclotron.  The natTi(α\,
 x) 51Cr reaction induced in Ti foils was used to monitor the incident beam
  intensity of about 100 nA. After a clean separation of radioplatinum\, th
 e radioactivity of 193mPt was measured via X-ray spectrometry using the Pt
  Kα1 X-ray line of 66.8 keV. The cross section of the 192Os(α\,3n) 193mP
 t reaction  reaches a value of about 1.5 b at the maximum at about 35 MeV.
  It was also calculated theoretically using the compound-precompound nucle
 ar model codes TALYS and STAPRE. The calculated values are consistent with
  the measured data. The optimum production of the 193mPt radionuclide via 
 this route was found in the range 30-38 MeV\; the integral yield of 193mPt
  amounted to 10 MBq/μAh. Its radionuclidic purity was found to be > 99% a
 nd the determined specific activity amounted to 1 GBq/μg Pt\, which is by
  about 103 higher than in reactor production. Thus basic information on th
 e production of high-quality 193mPt for therapeutic application is provide
 d.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=208&sessionId
 =26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=208&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:An Automated Production of  64Cu on 18/9 MeV cyclotron
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-148@cern.ch
DESCRIPTION:Speakers: Prof. RAJEC\, Pavol (BIONT\, Karloveská 63\, Bratis
 lava\, Slovakia)\nObjectives: The reaction route 64Ni(p\,n)64Cu is very po
 pular for the preparation of 64Cu because its entrance channel is accessib
 le at low energies and yield  of reaction is quite high. The objective is 
 to develop a module for automated production of 64Cu at BIONT site.\nMetho
 ds: Electrodeposition was performed in galvanostatic mode at current 10–
 100 mA. Electroplating was accomplished within 1.5–12 h. A thickness of 
 Ni layer was determined\nby calculation after weighing of Ni on a disk for
  1.13 cm2 area. A quality of surface layer was examined by SEM (scanning e
 lectron microscope). COSTIS target station was installed at the end of the
 external beam line of the IBA Cyclone 18/9 cyclotron. The target station h
 as been equipped with 300 µm Nb window foil in the front of the target to
  degrade energy to energy\nfor nuclear energy less than 14 MeV. The homoge
 neous beam with area of 1.2 cm2 with of 5 µA proton and energy less than 
 14 MeV was applied. An automated separation module for isolation of 64Cu e
 quipped with PLC SIMATIC S7-1200 controller has been developed. The qualit
 y of 64Cu was checked by gamma spectrometry and chemical purity (64Ni) was
  determined by ICP-MS. \nResults: The target was prepared by electrodeposi
 tion of nickel proceeds according to the Davison and Harrison [1] and Phil
 ip and Nicol [2] in ammoniacal solution at pH 9. Target was irradiated wit
 h current of 5 µA in the COSTIS target station. 64Cu production rate for 
 100 mg 64Ni of 99.09 % purity (ISOFLEX) on gold target was 104 MBq/µAh. T
 he separation of 64Cu from the target was achieved by anion exchange chrom
 atography with HCl as elution solution. The chemical purity of 64Cu produc
 t was checked by ICP MS and concentration of 64Ni was less than 2 ppm.\nCo
 nclusions: The procedure developed has been successfully applied for the r
 outine production of no-carrier-added 64Cu from enriched 64Ni generated by
  the reaction 64Ni(p\, n)64Cu using a cyclotron 18/9. An automated separat
 ion module with PLC SIMATIC S7-1200 remote control has been constructed fo
 r the preparation of 64Cu with good radionuclide and chemical purity.\nRes
 earch Support: This work was supported by the Slovak Research and Developm
 ent Agency under the contract No. VMSPP-0075-09.\n\nReferences: [1] Daviso
 n W\, Harrison JA (1972) The reduction of aqueous nickel ammine complexes.
  J Electroanal Chem 36:399–410\, [2] Philip HI\, Nicol MJ (1976) The ele
 ctrodeposition of nickel from ammoniacal solutions\, project report no. 18
 04. National Institute for Metallurgy\, Randburg\n\nhttp://indico.cern.ch/
 contributionDisplay.py?contribId=148&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=148&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Bioconjugated nanozeolites labeled with <sup>2
 23\,224\,225</sup>Ra
DTSTART;VALUE=DATE-TIME:20120917T142500Z
DTEND;VALUE=DATE-TIME:20120917T144000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-149@cern.ch
DESCRIPTION:Speakers: Prof. BILEWICZ\, Aleksander (Institute of Nuclear Ch
 emistry and Technology\, Poland)\nRa-223\, Ra-224 and Ra-225\, among other
 s alpha-emitting radionuclides\,  have attractive properties for use in ta
 rgeted radionuclide therapy. Unfortunately\, Ra2+ cations like other catio
 ns of the II group\, forms very weak complexes\, therefore labeling of the
  biomolecules with 223\,224\,225Ra is a very difficult task. On the other 
 hand\, some zeolites exhibit very high affinity for Ra2+ cations.\nIn our 
 studies we propose to use nanozeolite as a carrier for transportation of 2
 23\,224\,225Ra radionuclides to the tumor sites. Due to high ion exchange 
 affinity\, nanozeolites strongly bind radium cations and additionally\, as
  aluminosilicates\, nanozeolites could be easily attach to biomolecules by
  silanol-amine/carboxyl linkers. \nNanozeolite of type A (20-70 nm diamete
 r) were synthesized by hydrothermal method. Next\, the surface of the nano
 zeolites was modified by attaching polyethylene glycol (500 - 600 daltons)
  containing silanol group on the one end and active ester on the second en
 d. The obtained samples were examined for encapsulation of 224Ra and 225Ra
  (milked from 228Th/224Ra and 229Th/225Ra generators). The stability of ra
 diolabeled nanozeolites were examined in 0.9% NaCl\, 0.02 M PBS\, 0.001 M 
 cysteine and glutathione and human serum. In the case of 224Ra\, about 2% 
 of gamma-radioactivity was found in the solution\, which has been attribut
 ed to 212Pb - the decay product of 224Ra\, while\, in the case of  225Ra e
 ven above 15% of activity was found in the solution. The activity has been
  ascribed to 225Ac and 213Bi - the decay products of 225Ra. In the next st
 eps we plan to stabilize 225Ra and all daughter radionuclides in nanozeoli
 te structure. After that\, the conjugation of the modified nanozeolites wi
 th two vector peptides – octreotide and substance P will be made.\n\nhtt
 p://indico.cern.ch/contributionDisplay.py?contribId=149&sessionId=17&confI
 d=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=149&sessionId=1
 7&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Structural studies of actinide-peptide complexes
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-77@cern.ch
DESCRIPTION:Speakers: Dr. SAFI\, Samir (CNRS\, France)\nIn the wake of the
  Fukushima accident assessing the mechanisms governing radionucleide impac
 t on the environment (particularly the biosphere) is of great importance. 
 \nMost data available on the interaction of actinides with biological syst
 ems are based on physiological or biokinetic measurements\, with scarce in
 formation on the microscopic factors such as structure of the actinide coo
 rdination site within biological molecules (proteins\, peptides...). These
  biomolecules are essentially responsible for specific migration pathways 
 towards various organs in vivo. This structural data is essential for deve
 loping the understanding structure\, function and affinity interdependence
 . Here-in we describe an approach for structural elucidation of several ur
 anyle and europium (used as a trivalent actinide surrogate) biological com
 plexes combining both experimental and theoretical techniques.  \nthe disc
 ribed approach overcomes the intricacy of actinide chemistry combined with
  the complexicity  of protein tertiary structure by using  biomimetic pept
 ides. The chosen peptides cover a wide spectrum of  structural as well as 
 functional (amide\, carboxylate et phosphonate…) properties. Isothermal 
 calorimetric titration  provided primordial thermodynamic information  (af
 finity constant\, stoechiometry)\, additional  functional and structural a
 nalysis techniques (IR\,TRLFS\, EXAFS) led to elucidate the complexe's str
 ucture. In parallel  DFT calculations have been used to optimize the propo
 sed structures and fit the experimental data.\n\nhttp://indico.cern.ch/con
 tributionDisplay.py?contribId=77&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=77&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - The observation of a volatile compound formati
 on with Po and Bi during experiments with superheavy elements
DTSTART;VALUE=DATE-TIME:20120918T081000Z
DTEND;VALUE=DATE-TIME:20120918T082500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-76@cern.ch
DESCRIPTION:Speakers: Dr. EICHLER\, Robert (Paul Scherrer Institute\,Switz
 erland)\nSophisticated gas-phase chromatography experiments with superheav
 y elements Cn\, E113\, and Fl are performed using noble gas atmospheres as
  carrier gases with only trace amounts of oxygen and water mainly to ensur
 e the elemental state. Surprisingly\, during these experiments the gas pha
 se transport of volatile species of Po and Bi have been observed. Their de
 position behaviour on gold surfaces have been measured. The decay characte
 ristics of the observed isotopes showed that the observed transport is not
  related to any precursors such as Pb or Rn. The dew-point monitoring of t
 he gas and the pretreatment of the carrier gas with hot Ta-getters changed
  the trace gas composition and was shown to influence the formation of the
 se compounds dramatically. From these observations the formation of volati
 le hydride compounds was concluded\, opening up an interesting chemical sy
 stem for the investigation of the superheavy elements E115 and Lv.\n\nThe 
 work is presented on behalf of the PSI-University of Bern-FLNR-ITE collabo
 ration.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=76&sessi
 onId=20&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=76&sessionId=20
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:On the fast release of tracer elements from metallic hosts – a s
 tep towards vacuum chromatography
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-74@cern.ch
DESCRIPTION:Speakers: Dr. EICHLER\, Robert (Paul Scherrer Institut)\nThe m
 ost common way to chemically investigate transactinides since almost 50 ye
 ars is by using a gas based transport setup. The "gas-jet" method has prov
 ed to be very useful as a fast transport medium\, allowing investigations 
 of nuclei with half-lives down to about a second. However\, for sub-second
  nuclei gas-jet type transport has quite poor efficiency due to decay loss
 es. Transport in vacuum is much faster and could therefore be a solution t
 o this problem. Vacuum chromatography [1] is an intenisvely discussed and 
 promissing method that may be applied in the near future to investigate so
 me of the heaviest elements known. In a gas-jet system the evaporation res
 idues (EVRs) are stopped in the carrier gas itself. This is of course not 
 possible in a vacuum system. Therefore it is mandatory to find a new metho
 d for stopping the EVRs after their production in nuclear fusion reactions
 . One possible solution would be to use a very thin metal foil or a stack 
 of metal foils where the EVRs are implanted. However\, in order not to loo
 se the speed advantage a vacuum based setup\, it is necessary that the sub
 sequent thermal release of the EVR from the metal foil is very fast. We ha
 ve conducted initial experiments\, using the lighter group 13 and 14 homol
 ogues of E113 and Fl (E114) to determine suiteable catchermaterials and th
 e best methods to achieve fast release.\nThe model about the heat of mixin
 g from A.R. Miedema [2] was used to determine the potential catcher-materi
 als Ni\, Y\, Zr\, Nb\, Mo\, Hf\, W\, and Re. The experiments took place at
  the Philips cyclotron at Paul Scherrer Institute in Switzerland. Tracer-d
 oped host materials were produced by the implantation of the fusion produc
 ts from a Zn\, Cd\, Hg targets that was irradiated with 80-MeV 4He2+. Othe
 rwise\, proton induced reactions were used to produce tracers within the c
 atcher materials. Diffusion constants and activation energies could be det
 ermined for the various tracer-host material combinations. Using the princ
 iples from Crank [3]\, Borg\, and Dienes [4] it was possible to deduce rel
 ease rates at various annealing temperatures and for different foil thickn
 esses. A first on-line experiment was performed at the Oslo Cyclotron Labo
 ratory of the University of Oslo using fission products from proton induce
 d fission of uranium.\nUsing a model applied for the first time by Bakker 
 [5] it was possible to extrapolate diffusion values from the model experim
 ent and from values from literature to predict corresponding properties fo
 r transactinides. For a certain set of experimental parameters\, such as c
 atcher material thickness\, temperature\, and time\, it is possible to cal
 culate release rates of superheavy elements from the investigated host mat
 erials\, assuming that the desorption time of the segregated tracer nuclid
 e is not the time determining factor of the release process.\n[1]  I. Zvar
 a\, J. Radioanal. Nucl. Chem. 2010\, 286\, 597-602.\n[2]    A.R. Miedema\,
  J. Less-Common Met. 1976\, 46\, 67-83.\n[3] 	J. Crank\, Oxford University
  Press\, London\, 1975.\n[4]	R.J. Borg\, G.J. Dienes\, Academic Press\, Sa
 n Diego\, 1988.\n[5]	H. Bakker\, J. Less-Common Met. 1985\, 105\, 129-138.
 \n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=74&sessionId=26
 &confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=74&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:OPENING LECTURE - Radioanalytical techniques in natural environmen
 tal radioactivity determination
DTSTART;VALUE=DATE-TIME:20120921T090000Z
DTEND;VALUE=DATE-TIME:20120921T092000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-73@cern.ch
DESCRIPTION:Speakers: Prof. SMODIŠ\, Borut (Jožef Stefan Institute)\nIne
 xpensive analytical tools such as gamma spectrometric measurements are usu
 ally applied in radiological monitoring of contaminated areas. However\, d
 etection limits obtained by such methods may not fit for the purpose\, in 
 particular when biological materials are to be analysed\, so more sensitiv
 e techniques have to be considered. Appropriate option is radiochemical de
 termination involving alpha-spectrometric or beta-counting detection\, as 
 well as measurement following neutron activation. Radiochemical procedures
  for the determination of U-238\, Ra-226 and Pb-210 are presented and crit
 ically compared with the gamma spectrometric measurements\, as exemplified
  by a case study of the Žirovski vrh mine and milling facility in Sloveni
 a.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=73&sessionId=
 31&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=73&sessionId=31
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - TRIGA-SPEC: an apparatus for high-precision mass
  spectrometry and laser spectroscopy on short-lived neutron-rich radionucl
 ides produced at the research reactor TRIGA Mainz
DTSTART;VALUE=DATE-TIME:20120918T105000Z
DTEND;VALUE=DATE-TIME:20120918T111000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-72@cern.ch
DESCRIPTION:Speakers: Mr. SMORRA\, Christian (Max-Planck-Institut für Ker
 nphysik Heidelberg\, Ruprecht Karls-Universität Heidelberg\, Johannes Gut
 enberg-Universität Mainz\, Germany)\nHigh-precision measurements of groun
 d-state properties of exotic nuclides such as nuclear binding energies\, s
 pins\, radii\, and moments\, can be used to test nuclear models far away f
 rom the valley of stability. TRIGA-SPEC\, located at the research reactor 
 TRIGA Mainz\, aims to investigate the ground-state properties of short-liv
 ed fission products produced by thermal-neutron-induced fission of U-235\,
  Pu-239\, or Cf-249. These fission products are extracted from the product
 ion site with a gas-jet transport system into an ion source\, where an ion
  beam of the radioactive nuclides is formed. Subsequently\, the ions are m
 ass separated and prepared in a radiofrequency quadrupole cooler and bunch
 er for the experiments. The high-precision measurements are performed with
  the Penning-trap mass spectrometer TRIGA-TRAP and by collinear laser spec
 troscopy with TRIGA-LASER. These experiments serve also as a development p
 latform for MATS and LaSpec at the FAIR facility at GSI. Recent results of
  the experiments in offline operation and the status of the online couplin
 g to the TRIGA reactor for the radioactive ion beam production are reporte
 d.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=72&sessionId=
 21&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=72&sessionId=21
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Superheavy element 114 is a volatile metal
DTSTART;VALUE=DATE-TIME:20120918T084000Z
DTEND;VALUE=DATE-TIME:20120918T085500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-71@cern.ch
DESCRIPTION:Speakers: Prof. DÜLLMANN\, Christoph (University of Mainz + G
 SI Darmstadt + Helmholtz Institute Mainz\, Germany)\nThe experimental dete
 rmination of chemical properties of element 114 (E114) is among the hottes
 t topics in superheavy element research. A first experiment reported E114 
 to be highly volatile\, and to form weak physisorption bonds with Au surfa
 ces [1]. However\, the large uncertainties of the measured adsorption enth
 alpy covered a wide range in volatility\, which prevented the experiment f
 rom yielding an unambiguous answer concerning the chemical properties of E
 114. A noble gas-like behavior\, representing a break in the trend in grou
 p 14 in the periodic table\, would be in contradiction to many recent theo
 retical calculations\, which predict a higher volatility and inertness com
 pared to the lighter homolog Pb\, but a stronger metallic behaviour compar
 ed to Cn [2-4].\nWe have performed a gas phase chemical study of E114 usin
 g a combination of the TransActinide Separator and Chemistry Apparatus (TA
 SCA) to isolate single atoms of E114 [5]\, and the Cryo-Online Multidetect
 or for Physics and Chemistry of Transactinides (COMPACT) [6]\, a gas chrom
 oatography detector suitable for studying the interaction of single atoms 
 with metallic Au surfaces. The setup allowed studying elements covering a 
 broad range in volatility\, from the non-volatile heavy metal Pb to the no
 ble gas Rn\, at a very low background level. \nIn our experiment\, the vol
 atility of five elements was studied: the two superheavy elements E114 and
  Cn ( Z=112)\, their lighter homologs Pb and Hg\, and the noble gas Rn. Tw
 o element 114 decay chains\, one from288114 and one from 289114\, have bee
 n detected and indicate E114 to adsorb on Au surfaces at room temperature 
 [7]. The interaction of element 114 with Au is at least as strong as that 
 of Cn\, in contradiction with a previous experiment [1]. Our results show 
 element 114 to be the least reactive member of group 14\, but still a meta
 l.\n\n	References\n\n1.	Eichler\, R. et al.\, Radiochim. Acta 98\, 133-139
  (2010).\n2.	Pershina\, V. et al.\, J. Chem. Phys. 131\, 084713 (2009).\n3
 .	Pershina\, V. et al.\, J. Chem. Phys. 127\, 134310 (2007).\n4.	Zaitsevsk
 ii\, A. et al.\, Russ. Chem. Rev. 78\, 1173 (2009).\n5.	Düllmann\, Ch. E.
  et al. Phys. Rev. Lett. 104\, 252701 (2010).\n6.	Dvorak\, J. et al.\, Phy
 s. Rev. Lett. 100\, 132503 (2008).\n7.	Yakushev\, A. et al.\, submitted (2
 012).\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=71&session
 Id=20&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=71&sessionId=20
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Preparation of TBq Activity 7Be from SINQ Cooling Water
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-70@cern.ch
DESCRIPTION:Speakers: Mrs. STOWASSER\, Tanja (Paul Scherrer Institut\, Swi
 tzerland)\n7Be is an important radionuclide for investigations of several 
 astrophysical processes and phenomena. The study of the destruction of 7Be
  during the first 10-15 minutes of Big Bang Nucleosynthesis (BBN) via the 
 7Be(n\,alpha)alpha reaction could help to understand the longstanding prob
 lem in BBN theory - the disagreement of the predicted abundance of primord
 ial 7Li with the observed one. Another application of 7Be is the study of 
 key reactions concerning the solar neutrino flux\, in particular the react
 ion 7Be(p\, γ)8B.\n10Be and its daughter products have been used to exami
 ne soil erosion\, soil formation from regolith\, as well as variations in 
 solar activity and the age of ice cores. One of the "hot topics" is the ha
 lf-life of 10Be\, where the literature values differ from 1.34 to 1.51 My.
  Two very recent measurements support rather the lower value: 1.388 My and
  1.386 My [1\, 2]. Additional measurements are\, therefore\, urgently need
 ed. One possibility is the use of LSC for the determination of the activit
 y and ICP-MS for measuring the number of atoms. The mass-bias calibration 
 of the ICP-MS requires at least 2 mass points in known amounts and since B
 e has only one stable isotope (9Be)\, 7Be can serve as the second marker.\
 nAnother application area of this interesting and rare isotope is the deve
 lopment of new construction materials\, requiring sensitive methods for st
 udying their wear resistance. Implantation of 7Be and follow up the change
 s of its activity can determine wear-out less than a micrometer.\n7Be is p
 roduced in considerable amounts in the cooling water (D2O) of the Spallati
 on Induced Neutron Source (SINQ) facility at PSI by spallation reactions o
 n 16O with the generated fast neutrons. By-products can be nearly neglecte
 d\, so that this cooling water establishes an ideal source for highly acti
 ve 7Be-samples.\nA shielded ion-exchange filter containing 100 ml of the m
 ixed-bed ion exchanger LEWATIT was installed as a by-pass for the cooling 
 water into the cooling circle of SINQ for 6 weeks. The collected activity 
 of 7Be was in the range of several hundreds GBq. Further the 7Be was separ
 ated and purified in a hot-cell installed\, remote-controlled separation s
 ystem. The facility is capable for production of 7Be with activities up to
  1 TBq per year.\n1. G. Korschinek et al.\, doi:10.1016//j.nimb.2009.09020
 \n2. J. Chmeleff et al.\, doi:10.1016/j.nimb.2009.09012\n\nhttp://indico.c
 ern.ch/contributionDisplay.py?contribId=70&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=70&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Development of actinide liquid scintillating target
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-79@cern.ch
DESCRIPTION:Speakers: Dr. AUPIAIS\, Jean (CEA DAM DIF\, France)\nWe presen
 t the development of a new kind of active actinide target\, based on organ
 ic liquid scintillators containing the dissolved isotope that can be used 
 for fission studies\, but also for (n\,xn) reactions measurements and pote
 ntially for radiative capture experiments. Amongst many advantages one can
  mention the very high detection efficiency\, the Pulse Shape Discriminati
 on capability\, the fast response allowing high count rates and good time 
 resolution and the ease of fabrication. The response of this target to fis
 sion fragments has been studied because the response of organic liquid sci
 ntillators to fission fragments is almost unknown. In the present work the
  response to fission events was also obtained with a 252Cf source. Several
  kinds of scintillators were used. Especially it was shown that a scintill
 ator based on Di Isopropyl Naphthalene (DIN) solvent with the PBBO scintil
 lating molecule lead to a very good separation between fission and proton 
 recoils The light quenching against the actinide dissolved mass has been c
 haracterized. For uranium even if a strong quenching is observed\, concent
 rations up to 10 mg/mL can be envisaged depending on the experiment to be 
 performed and on the geometry of the active target. For thorium no quenchi
 ng was observed. The discrimination of alpha\, fission and proton recoil e
 vents is demonstrated. The alpha decay and fission detection efficiencies 
 are simulated and compared to measurements. Finally the use of such a targ
 et in the context of fast neutron induced reactions is discussed.\n\nhttp:
 //indico.cern.ch/contributionDisplay.py?contribId=79&sessionId=26&confId=1
 83405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=79&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Preparation of spiked grass for use as environmental radioactivity
  calibration standard
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-205@cern.ch
DESCRIPTION:Speakers: Dr. LOURENÇO\, Valerie (CEA\, LIST\, LNE-Laboratoir
 e National Henri Becquerel\, 91191 Gif-sur-Yvette Cedex\, France)\nThe mon
 itoring of environmental radioactivity is important for public health prot
 ection. It is all the more important as the radionuclides can enter the fo
 od chain. Environmental nuclear analysis is usually carried out using γ-r
 ay spectrometry on homogenized raw or treated materials (i.e. dried\, siev
 ed or ashed samples). The composition and density of environmental monitor
 ing samples are very different from a sample to another. \nThe Laboratoire
  National Henri Becquerel (LNE-LNHB)\, as the French primary laboratory in
  the field of ionizing radiation\, is working on the production of suitabl
 e calibration standards to improve the traceability chain of environmental
  radioactivity measurements. To address this issue\, LNE-LNHB intends to p
 roduce mixed γ-ray calibration standards with certified mass activity and
  composition as representative of real environmental samples as possible. 
 The use of such standards\, suitable in radionuclide composition and densi
 ty\, will also improve the measurement system calibration due to a more ac
 curate correction of self-attenuation by measuring a known sample whose co
 mposition is close to the real ones.\nThe paper describes the preparation 
 and characterization of a low density matrix made of treated real grass sp
 iked with mixed γ-ray emitters. The composition of the spiking cocktail i
 ncludes low energy γ-ray emitters to account for self-attenuation in the 
 matrix and high energy γ-ray emitters to cover a wide energy range. Multi
 - γ emitters have also been included to test the ability to estimate coin
 cidence corrections. The spiking yield of the matrix is assessed and the h
 omogeneity of the batch is verified by variance analysis on subsamples. \n
 A proficiency test is being organized with the resulting matrix. The sampl
 es are to be shipped on mid-September so\; unfortunately the results of th
 e intercomparison will not be known by the time of the conference.\n\nhttp
 ://indico.cern.ch/contributionDisplay.py?contribId=205&sessionId=26&confId
 =183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=205&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - Fukushima fallout at Thessaloniki\, Greece (40
 ºN) and Milano\, Italy (45ºN)
DTSTART;VALUE=DATE-TIME:20120921T105500Z
DTEND;VALUE=DATE-TIME:20120921T111000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-2@cern.ch
DESCRIPTION:Speakers: Prof. GROPPI\, Flavia (LASASegrate\, Università deg
 li Studi di Milano\, Italy)\nAn earthquake of magnitude 9.0 occurred on Ma
 rch 11\, 2011 on the Pacific Ocean side of northern Honshu\, Japan\, follo
 wed by a tsunami that struck the east coast of the Tohoku region and cause
 d a serious nuclear accident at the Fukushima Daiichi Nuclear Power Plant.
  The contaminated air masses were transported across the Pacific towards t
 he North American continent\, Europe and Central Asia  despite dispersion 
 and washout along the trip. Radionuclides such as 131I\, 134Cs\, and 137Cs
  were detected in different locations throughout Europe. \nRight after the
  Fukushima reactor accident\, systematic analysis of environmental samples
  was undertaken in order to detect and quantitatively determine the radion
 uclides due to the Fukushima fallout in Milano and Northern regions\, Ital
 y\, by LASA Laboratory of the INFN (Instituto Nationale di Fisica Nucleare
 ) Sez. of Milano and in Thessaloniki\, Greece by the Laboratory of Radiati
 on Physics. The concentrations of 131I\, 134Cs\, and 137Cs mainly in air a
 nd water\, which control the main way of deposition of the radionuclides i
 n the soil surfaces\, vegetables and food chain\, were determined. Further
 more analysis of soil\, grass and milk samples in both sites of investigat
 ion were taken place. The estimated effective doses for population related
  to the contributions of Fukushima fallout due to different pathways were 
 very far below levels of concern.\nThis work gives the extent of contamina
 tion in Northern Greece and in Northern Italy due to Fukushima fallout and
  interprets the measured activities at the site of investigation as these 
 resulted from a complicated air mass transport. For the interpretation of 
 activity variations of measured radionuclides\, the NOAA HYSPLIT backward 
 trajectories model has been used to assess the transport pattern.\n\nhttp:
 //indico.cern.ch/contributionDisplay.py?contribId=2&sessionId=31&confId=18
 3405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=2&sessionId=31&
 confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:A warm welcome from the Division of Nuclear and Radiochemistry (DN
 RC) of EuCheMS
DTSTART;VALUE=DATE-TIME:20120917T060000Z
DTEND;VALUE=DATE-TIME:20120917T062000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-263@cern.ch
DESCRIPTION:Speakers: Prof. GAEGGELER\, Heinz (Paul Scherrer Institut\, Sw
 itzerland)\nDNRC is one of 18 divisions or working parties that form the E
 uropean Association of Chemical and Molecular Sciences (EuCheMS)\, founded
  in 2004. EuCheMS is an umbrella organisation of European National Chemica
 l Societies promoting the outreach of chemical science and technology to o
 ur society as well as to all relevant political organisations. Therefore\,
  the headquarter of EuCheMS is in Brussels. \nDNRC represents the field of
  nuclear sciences in EuCheMS in its manyfold facets\, from basic research 
 to a broad field of applications. EuCheMS organizes a congress every secon
 d year\; the last one was very recently between 26 and 31 August 2012 in P
 rague (4ECC). \nDNRC contributed to 4ECC with three sessions\, namely on i
 ) Fukushima & Chernobyl\, ii) Applications of Radiotracers to Environmenta
 l Sciences\; and iii) Speciation of (mostly) Actinide Compounds. These thr
 ee sessions were part of a Symposium on Chemistry and Environment.\nEach d
 ivision of EuCheMS has the obligation to organize a European conference in
  its field every second year. DNRC decided to take already existing confer
 ence series to meet this requirement\, the Nuclear and Radiochemsitry  Con
 ferences (NRC) und the Radiochemistry Conference Series (RadChem) organize
 d by our Czech colleagues in Marianske Lazne. Both Conferences Series are 
 organized  every four year.\nNRC was initiated in 1984 by Prof. K.H. Liese
 r from Germany. Since then it was hosted by France\, England\, Austria\, S
 witzerland\, Germany and Hungary. We are very happy that our Italian Radio
 chemistry colleagues invited NRC8 to be held in their home country. We are
  looking forward to a stimulating and scientifically challenging conferenc
 e discussing the forefront achievements in nuclear chemistry and in radioc
 hemistry in the beautiful environment of Como.\n\nhttp://indico.cern.ch/co
 ntributionDisplay.py?contribId=263&sessionId=6&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=263&sessionId=6
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:EC Interlaboratory Comparison on Radionuclides in Dried Bilberries
DTSTART;VALUE=DATE-TIME:20120919T160000Z
DTEND;VALUE=DATE-TIME:20120919T175000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-144@cern.ch
DESCRIPTION:Speakers: Dr. MEREŠOVÁ\, Jana (Institute for Reference Mater
 ials and Measurements\, Belgium)\nThe Euratom Treaty obliges Member States
  of the European Union to perform measurements of the radioactivity on the
 ir territories and to report the results to the European Commission. There
 fore\, regular European comparisons are conducted in order to verify the p
 erformance of the monitoring laboratories. In 2011\, the Institute for Ref
 erence Materials and Measurements (IRMM) organised an interlaboratory comp
 arison (ILC) for the activity concentrations of three radionuclides (40K\,
  90Sr\, 137Cs) in dried bilberry powder. The Fukushima accident underlined
  the importance of radioactivity monitoring in food\, and the need for com
 parisons and proficiency tests as a tool to provide reliable measurement r
 esults. \n\nThe candidate reference material IRMM-426 Wild Berries was use
 d as a testing material. The berries were collected in the region affected
  by the Chernobyl accident. Due to the natural uptake from elevated levels
  in the environment\, the radionuclides 137Cs and 90Sr were metabolised by
  the plants\, hence no spiking was required. The material was processed at
  IRMM and the reference values traceable to SI units and SIR were establis
 hed in the CCRI(II) supplementary comparison in which nine National Metrol
 ogy Institutes participated [1]. \n\nIn total\, 88 monitoring laboratories
  participated in this ILC. They were free to use methods of their own choi
 ce\, preferably the routine procedures used in their laboratories. The mea
 surement procedures used by the participants are discussed in this paper i
 n an overview of methods. The results of the participating laboratories we
 re evaluated versus the reference values. A robust evaluation of the perfo
 rmance of individual laboratories was performed using relative deviations 
 and En numbers [2]. \n\nThe activity concentrations of 137Cs and 40K were 
 determined almost exclusively by gamma-ray spectrometry with 9 % and 18 % 
 of results deviating more than 20 % from the reference values of (772 +/- 
 32) Bq•kg-1 and (250 +/- 17) Bq•kg-1\, respectively. These results are
  worse in comparison to previous ILCs. This may be due to the food matrix 
 and inappropriate use of corrections for differences in density and/or geo
 metry between sample and standard sources of activity. In the case of 90Sr
 \, about 77 % of results lie within 20 % from the reference value of (153 
 +/- 8) Bq•kg-1 and 69 % of results are En compatible. This is much more 
 favourable than observed in previous exercises.  \n\nThis comparison demon
 strates that several laboratories have difficulties to determine activity 
 concentrations of 137Cs and 40K in food samples. The relative success in t
 he 90Sr determination might be attributed to the easier separation of stro
 ntium from the dried fruit matrix compared to milk powder or soil in earli
 er comparisons.   \n\n\n[1]	U. Wätjen et al. Appl. Radiat. Isot. In press
 .\n[2]	ISO/FDIS 13528:2005(E)\, Statistical methods for use in proficiency
  testing by interlaboratory comparisons\, ISO\, Geneva (2005).\n\nhttp://i
 ndico.cern.ch/contributionDisplay.py?contribId=144&sessionId=26&confId=183
 405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=144&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Separation of actinium-225 for nuclear medicine purposes from thor
 ium targets irradiated by high energy protons
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-262@cern.ch
DESCRIPTION:Speakers: ALIEV\, Ramiz (Moscow State University\, Russia)\nDu
 e to high linear energy transfer (LET) of about 100 keV/µm and low path o
 f about 50-100 µm in biological tissue of alpha particles\, alpha-emitter
 s are promising for targeted radiotherapy of cancer. The number of potenti
 al alpha-emitters that could be used in medical applications is limited by
  the requirements of half-life\, availability of these alpha-emitters and 
 experimental difficulties in their separation. The most promising candidat
 es for clinical applications are 211At\, 212Bi\, 213Bi\, 225Ac. Among thes
 e alpha-emitters\, 211At could be easily obtained by irradiation of bismut
 h by 28-29 MeV alpha-particles on a cyclotron. However its application is 
 limited by the synthetic preparation of astatineorganic compounds and weak
 ness of At-C chemical bond. Actinium-225 could be used either directly for
  preparation of radioimmunoconjugates or could be used as a parent radionu
 clide in 213Bi isotope generator. However wide application of 213Bi and 22
 5Ac is limited by the low availability of these radionuclides. Several met
 hods are proposed for 225Ac production while most frequently it is separat
 ed from mother 229Th or by irradiation of 226Ra with protons in a cyclotro
 n. Both methods have some practical limitations to be applied routinely. \
 nThe aim of this investigation was to develop the separation method of 225
 Ac from natural thorium irradiated with protons with the energy of around 
 100 MeV at linear accelerator of Institute of Nuclear Research RAS.\nThori
 um foil was irradiated by protons with the energy of 104 MeV. The radionuc
 lide composition was determined by gamma-spectrometry. Irradiated thorium 
 target was dissolved in minimal volume of 6 M HCl upon heat. Thorium and s
 ome fission products were separated by solvent extraction by TPB in toluen
 e (1:1) (twice) and by 0.15 M TOPO in toluene. In some experiments dissolu
 tion was done by 7 M HNO3 and extraction was also done from this solution.
  Aqueous phase containing actinium was evaporated near dryness and dissolv
 ed in 0.05 M HNO3. These solutions was transferred to the extraction chrom
 atographic column filled with Ln Resin (Eichrom) After adding the sample t
 o the column\, it was sequentially washed by 0.05 M HNO3 and 3 M HNO3 solu
 tions. Actinium and REE containing fraction were loaded to the extraction 
 chromatographic column filled with TRU Resin (Eichrom). To determine the i
 mpurities of 227Ac in actinium fraction the alpha-spectrometry was employe
 d. Other radionuclidic impurities were assessed by gamma ray spectrometry.
  It was shown that most significant impurity is 227Ac (less than 0.1% on E
 OB) but it could not interfere in application of the product in Ac/Bi gene
 rators.\n\nhttp://indico.cern.ch/contributionDisplay.py?contribId=262&sess
 ionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=262&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:The influence of iron on the efficiency of the 68Ga labeling of DO
 TATOC and simple colorimetric determination of iron
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-261@cern.ch
DESCRIPTION:Speakers: Dr. MUELLER\, Dirk (Department of Nuclear Medicine\,
  Zentralinik Bad Berka\, Germany)\nIntroduction\n\nIt is well known that i
 ron ions have a strong impact on the labeling efficiency of DOTA-peptides 
 with 68Ga. In a draft for a monograph of 68Ga-chloride for the European Ph
 armacopoeia (PHARMEUROPA\, Vol. 23\, No. 3\, July 2011) a maximum concentr
 ation for iron is given with 10 µg/GBq. The concentration should be deter
 mined by atomic absorption spectrometry.\nEasier to handle but high sensit
 ive and specific colorimetric test systems would have many advantages for 
 clinical production of radiopharmaceuticals. Moreover\, the European Pharm
 acopoeia describes well known methods for colorimetric determination of th
 e total heavy metal concentration in pharmaceuticals and starting material
 s. \nIn this work we quantify the influence of iron and investigate the pr
 actical application of a  colorimetric test\, which is able to determine l
 ower iron concentrations than required.   \n\nMethods \n\nFor the labeling
  of DOTATOC the NaCl based method (Mueller et al. \, Bioconjugate Chem.\, 
 2012\, 23 (8)\, pp 1712–1717) was used. A stock solution of iron(III) wa
 s prepared by dissolving of iron(III)-chloride in 0.1 M HCl. Different amo
 unts of iron were added into the reaction vessels prior to the addition of
  68Ga and the pH of the reaction mixtures were adjusted with sodium acetat
 e buffer.\nAfter heating the ratio between peptide-bound and free 68Ga was
  determined by radio HPLC (RP-18 column\; solvent A water\, solvent B acet
 onitrile\, gradient 5-95%\, 0-15 min).  \nThe concentration of iron was cr
 oss-checked by a colorimetric test system (VWR\, Microquant Iron Test\, me
 thod colorimetric\, Ferrospectral\, 0.1- 5 mg/ml Fe).\n\nResults\n\nWe cou
 ld impressively show that the colorimetric iron test\, cross-checked by a 
 self made iron standard\, safely determines the iron concentration in the 
 reaction mixture or the eluate. The sensitivity of this test is hundred ti
 mes higher than required. If 50 µg DOTATOC were used\, a content of iron 
 up to 0.6 µg shows a successful labeling but already 2 µg iron leads to 
 an incomplete labeling. In this case the concentration of free 68Ga in the
  final reaction mixture is higher than 10 %.  The use of 40 µg DOTATOC an
 d 2 µg iron in the reaction mixture makes a successful labeling impossibl
 e. The concentration of 68Ga in the final reaction mixture is then higher 
 than 90 %. After addition of 6 µg iron and the use of 50 µg DOTATOC the 
 final concentration of free 68Ga amounts 48%. A prior concentration step w
 ith the help of a cation exchanger cartridge collects also iron(III) and i
 t can be also eluted completely with an eluent for 68Ga-chloride. The tota
 l amount of iron in the  68Ge/68Ga generator eluate reaches therefore into
  the reaction mixture and would influence the labeling.\n\nConclusion\n\nA
  content of 10 µg iron in the 68Ge/68Ga generator eluate would prevent a 
 successful labeling of DOTA conjugated peptides. The colorimetric determin
 ation of iron is particular well suited to detect iron incorporation in th
 e eluate or in the reaction mixture. This test system is much easier to ha
 ndle than an atom absorption spectrometer in the clinical practice. Furthe
 rmore we assume that the established colorimetric test on heavy metals for
  pharmaceuticals and starting materials as describe in the European Pharma
 copoeia would safely show toxicological concentrations on these cations.\n
 \nhttp://indico.cern.ch/contributionDisplay.py?contribId=261&sessionId=26&
 confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=261&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:ORAL PRESENTATION - A new route for polonium-210 production from a
  bismuth-209 target
DTSTART;VALUE=DATE-TIME:20120919T083000Z
DTEND;VALUE=DATE-TIME:20120919T084500Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-41@cern.ch
DESCRIPTION:Speakers: Mr. YOUNES\, Ali (SUBATECH laboratory (UMR 6457)\, N
 antes 44307\, France)\nA new method is proposed for the production and pur
 ification of polonium-210 (Po-210). This method is based on the bombardmen
 t of a bismuth-209 (Bi-209) target with a 38 MeV alpha particle beam that 
 conducts to the production of astatine-210 (8.1 hrs) which decays to Po-21
 0. It is further purified from bismuth target by a wet method using a liqu
 id –liquid extraction process with tributyl phosphate (TBP). The main ch
 allenge relies on the separation of traces of Po-210 from a solution conta
 ining macroscopic quantities of bismuth. Several parameters were studied (
 acidity\, aqueous medium\, extraction time\, TBP dilution\, organic solven
 t) for defining the best conditions. The retained purification process con
 sists in four steps: (i) the dissolution of the Bi target in nitric acid 1
 0M followed by a reconditioning in 7M HCl\, (ii) the extraction of Po-210 
 in 90% TBP in para xylene (iii) washing of the organic layer with 7M HCl a
 nd (iv) the back extraction of Po-210 in 9M nitric acid. The optimised pro
 cess leads to a solution of Po-210 with a global recovery yield of 93 % wi
 th good radionuclide and chemical purities. The obtained data allow as wel
 l proposing an extraction mechanism of Po-210 by TBP.\n\nhttp://indico.cer
 n.ch/contributionDisplay.py?contribId=41&sessionId=23&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=41&sessionId=23
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Review of Mo-99 and other reactor radionuclide p
 roduction in RIAR in terms of world demands
DTSTART;VALUE=DATE-TIME:20120919T081000Z
DTEND;VALUE=DATE-TIME:20120919T083000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-260@cern.ch
DESCRIPTION:Speakers: Dr. KUZNETSOV\, Rostislav (Research Institute of Ato
 mic Reactors\, Russia)\nProduction of Mo-99 was established in Russia more
  than 20 years ago. First facilities were placed at the Institute of Physi
 cs and Power Engineering  and Karpov Physico-Chemistry Research Institute 
 (both in Obninsk city). They were focused on domestic supply and had limit
 ed production capacity. The IPPE facility was shut-down a few years ago. T
 he Karpov Insititute’ facility continues its operation.\nPrincipal decis
 ion were made in late 2009 by Russian Government to establish a new produc
 tion facility – modern\, providing prospective needs of nuclear medicine
  actively developing in Russian Federation\, and increasing export capabil
 ities of Russian isotope producers as well. The concept of this new produc
 tion plant is aimed in providing large-scale\, reliable\, sustainable and 
 continuous supply of the product\, which is fully complied with Internatio
 nal Pharmacopeia requirements. The process should be realized on a contemp
 orary equipment and control systems\, comply with GMP requirements and be 
 environmentally safe.   \nTo provide continuous production two pool-type r
 eactors (RBT-6 and RBT-10) are used for irradiation. Their current irradia
 tion capacity allows for irradiation up to 4 targets/week\, providing 2-2.
 2 kCi/target at EOB. The number of irradiation positions can be increased 
 twice in a nearest future.\nThe facility for irradiated targets processing
  was constructed at Research Institute of Atomic Reactors site (Dimitrovgr
 ad) during 2010  - mid 2012 jointly with Isotope Technology Dresden (ITD\,
  Germany)\, that is a part of  Gamma Service Group International\, GmbH (S
 witzerland). The ITD Company has provided the ROMOL-99 process\, and princ
 ipal set of equipment for processing as well we radiation safety systems (
 Xe-trapping line\, iodine filter tower). The first production line was des
 igned and constructed by December\, 2010\, it was tested and improved duri
 ng first half of 2011. The production was started in August\, 2011\, first
  batches of Mo-99 were supplied to Russian producer of 99Mo/99mTc-generato
 rs. During late 2011 – 2012 considerable improvements were made in the p
 rocess operation mode\, ensuring Mo-99 radiochemical yield appox. 80%\, an
 d product quality corresponding to European Pharmacopeia requirements. \nT
 he second production line was installed in a new building\, constructed du
 ring 2011-2012. The facility consists of two independent sets of equipment
  (dissolvers\, vessels for solution\, systems for Mo-99 isolation and puri
 fication) thus providing increased production capacity of the entire facil
 ity and reliable operation of the plant.  Some equipment units (container 
 transport system\, targets\, wastes handling\, vessels for temporary stora
 ge ets.) that do not effect the production capacity\, are used jointly thu
 s decreasing cost of the entire facility. The second facility was assemble
 d late June\,  2012\, and currently it is on the commissioning. Regular fu
 ll-scale production is scheduled for November-December\, this year. \nFor 
 more than 30 years RIAR routinely produces wide spectrum of reactor radion
 uclides. The Institute is a principal (the only in Eastern hemisphere) pro
 ducer 252Cf and other transplutonium elements (Cm-244\,248\, Am-241\,243\,
  Bk-249). Production of these radionuclides is possible due to unique high
 -flux reactor SM operated by RIAR. They are supplied mainly as sealed sour
 ces\, produced by original technologies. The resent achievement of RIAR is
  production of Cm-244 alpha-sources for APX spectrometer that was successf
 ully landed on a Mars planet last August. \nAvailability of high-density n
 eutron fluxes (>2.1015 cm-2s-1) allows for production of high-specific act
 ivity radionuclides\, that is a principal feature of RIAR. They are Co-60 
 (>250 Ci/g)\, Se-75 (>1200 Ci/g)\, Ni-63 (up to 12 Ci/g)\, W-188 (up to 8 
 Ci/g)\, Lu-177 (>90 kCi/g)\, n.c.a. I-131\, I-125\, etc. In a number of ca
 ses fast flux BOR-60 reactor is used for irradiation\, producing Gd-153 (>
 100 Ci/g)\, n.c.a. Sr-89 (>3000  Ci/g).\n\nhttp://indico.cern.ch/contribut
 ionDisplay.py?contribId=260&sessionId=23&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=260&sessionId=2
 3&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Sequential separation and determination of Pu\, Sr-90 and Am-241 i
 n soil and sediment samples using DGA Resin for the preconcentration of th
 e actinides.
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-47@cern.ch
DESCRIPTION:Speakers: Dr. JÄGGI\, Maya (Radioanalytics - Paul Scherrer In
 stitut\, Switzerland)\nA method for the sequential\, and quantitative\, se
 paration of Pu\, Sr-90 and Am-241 radionuclides in environmental soil and 
 sediment samples is presented (oder: has been developed). After wet- and d
 ry-ashing of the samples\, Pu and Am-241 were preconcentrated from the lea
 ching solution on DGA resin\, whereas Sr-90 was not retained and collected
  in the eluate. Pu was then separated from Am-241 using an anion exchange 
 resin (BioRad AG 1-X2) and  was further purified by UTEVA and DGA resins i
 n series. Am-241 was separated from the lanthanides using a TEVA column. I
 n parallel\, Sr-90 was purified by a Ca-oxalate precipitation followed by 
 separation on Sr resin. The measurements of Pu and Am-241 were performed b
 y α-spectrometry. Sr-90 was measured by low-level liquid scintillation co
 unting. The developed method was validated by analyzing IAEA reference mat
 erials and environmental soil samples.\n\nhttp://indico.cern.ch/contributi
 onDisplay.py?contribId=47&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=47&sessionId=26
 &confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:INVITED LECTURE - Nuclear and Radiochemistry Training in the Europ
 ean system of Accumulation and Transfer of Credits for Vocational Educatio
 n and Training in Europe (ECVET)
DTSTART;VALUE=DATE-TIME:20120920T124000Z
DTEND;VALUE=DATE-TIME:20120920T130000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-267@cern.ch
DESCRIPTION:Speakers: Dr. RETEGAN\, Teodora (Chalmers University of Techno
 logy)\nECVET is based on concepts and processes\, which are used in a syst
 ematic way to establish a common and user-friendly language for transparen
 cy\, transfer and recognition of learning outcomes in Europe. The European
  Parliament and the Council have adopted ECVET in 2009 and since then a nu
 mber of projects dealing with implementation of ECVET have started.\nEleve
 n projects between 2008-2011 and eight between 2011-2014 respectively have
  been running\, which are funded through the centralized actions of Livelo
 ng Learning Programme. A series of other projects\, funded by national pro
 grammes or other European funding schemes not directly interested in credi
 t transfer are also on-going.\nNuclear and Radiochemistry Training in the 
 ECVET European system is going to be further discussed\, with examples. A 
 series of achievements are going to be highlighted\, as well as the limita
 tions and opportunities in the present context in nuclear field.\n\nhttp:/
 /indico.cern.ch/contributionDisplay.py?contribId=267&sessionId=29&confId=1
 83405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=267&sessionId=2
 9&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Liquid-phase Studies of Seaborgium using the Automated Liquid-liqu
 id Extraction system SISAK
DTSTART;VALUE=DATE-TIME:20120917T153000Z
DTEND;VALUE=DATE-TIME:20120917T170000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-126@cern.ch
DESCRIPTION:Speakers: Dr. OMTVEDT\, Jon Petter (Univ. Oslo\, Norway)\nSISA
 K is an automated liquid-liquid extraction system adopted to one-atom-at-t
 ime studies of transactinide elements [1]. It is directly connected to flo
 w-through Liquid-Scintillation (LS) detection cells for unique identificat
 ion of a given transactinide using alpha-alpha correlations and Pulse-Shap
 e Discrimination (PSD) of beta- and gamma-induced events [2]. The system w
 orks behind a physical gas-filled preseparator to significantly reduce unw
 anted products from the target. This method was developed and demonstrated
  at Lawrence Berkeley National Laboratory using the Berkeley Gas-filled Se
 parator (BGS) [1\,2] and 257Rf produced in a 50Ti on 208Pb reaction. It wa
 s the first time such a separator was used for a transactinide chemistry e
 xperiments and was very successful. Follow-up experiments [3] where perfor
 med which firmly established the SISAK system as suitable for liquid-phase
  studies of transactinide elements\, provided a physical preseparator like
  the BGS is used to eliminate unwanted products. \n\nRecently\, a collabor
 ation between researchers at the Japan Atomic Energy Agency´ (JAEA) Advan
 ced Science Research Centre (ASR) at Tokai and University of Oslo was form
 ed to perform liquid-phase chemistry experiments on seaborgium\, element 1
 06. The experiments will be performed at the Nishina Centre for Accelerato
 r Based Science\, RIKEN\, using the GARIS gas-filled separator. Model and 
 development experiments have been and will continue to be performed at the
  Tokai Tandem-accelerator and the Oslo Cyclotron Laboratory.\n\nThe SISAK 
 system will be set up with an electrochemical cell to enable redox experim
 ents to deduce important and basic chemical information about seaborgium\,
  see NRC8 contribution by A. Toyoshima et al. for further details. For thi
 s to work SISAK must be adopted to provide equally rapid transfer as the s
 ystem used at LBNL (average transport time of 20 s)\, but with lower flow-
 rate (0.1-0.2 mL/s compared to 0.4-0.5 mL/s used in Berkeley). The major o
 bstacle to achieve this is the transfer and dissolution of the metal-ions 
 attached to KCl aerosol-particles from the gas-jet transport and into the 
 first liquid phase: When the liquid-flow goes down the volume ratio betwee
 n liquid and gas gets more and more disadvantageous\, leading to significa
 nt yield loss in this stage. A new device\, based on membrane separation\,
  was constructed which in tests at OCL have shown yields above 80 % even f
 or flow-rates down to 0.1 mL/s\, something which has never been achieved w
 ith the old centrifuge degasser [4]. Due to its simplicity the new device 
 it is also much faster than the old degasser. Work is in progress to final
 ize the design and implementation with the SISAK system\, results which wi
 ll be reported at NRC8 together with the overall plan for investigating se
 aborgium.\n\n \nReferences:\n[1] J.P. Omtvedt\, et al.\, J. Nucl. Radioche
 m. Sci. 3 (2002) p. 121.\n[2] L. Stavsetra et al.\, NIM A543\, (2005) p. 5
 09\n[3] L. Zheng\, PhD-thesis: " Preparation for Liquid-Liquid Extraction 
 Studies of Dubnium Using Homologue Models with the SISAK System"\, Oslo un
 iversity 2007 (http://www.mn.uio.no/kjemi/english/research/projects/sisak/
 publications/thesies/LZheng_LLE_Dubnium_development_for_SISAK_PhD_Thesis_2
 007.pdf)\n[4] K. Ooe\, H. V. Lerum\, and J. P. Omtvedt\, manuscript in pre
 paration for publication.\n\nhttp://indico.cern.ch/contributionDisplay.py?
 contribId=126&sessionId=26&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=126&sessionId=2
 6&confId=183405
END:VEVENT
BEGIN:VEVENT
SUMMARY:Panel Discussion - ● Introduction: Prof. J. Lehto\; ● Panelist
 s - 3 minutes per panel member\; ● Discussion: 10 minutes\; ● Panel Su
 mmary: 5 minutes
DTSTART;VALUE=DATE-TIME:20120920T133500Z
DTEND;VALUE=DATE-TIME:20120920T143000Z
DTSTAMP;VALUE=DATE-TIME:20130524T162835Z
UID:indico-contribution-183405-266@cern.ch
DESCRIPTION:Speakers: SHI\, Weiqun (Chinese Academy of Sciences)\, REICH\,
  Tobias (Johannes Gutenberg-Universität Mainz)\, BONARDI\, Mauro L. (UNIM
 I and INFN - Milano)\, YOKOYAMA\, Akihiko (Kanazawa University)\, NARBUTT\
 , Jerzy (Institute of Nuclear Chemistry and Technology)\, ALIEV\, Ramiz (M
 oscow State University)\, TÜRLER\, Andreas (Paul Scherrer Institute & Ber
 n University)\, NITSCHE\, Heino (UC Berkeley &LBNL)\nhttp://indico.cern.ch
 /contributionDisplay.py?contribId=266&sessionId=35&confId=183405
LOCATION:Como\, Italy
URL:http://indico.cern.ch/contributionDisplay.py?contribId=266&sessionId=3
 5&confId=183405
END:VEVENT
END:VCALENDAR