Jun 2 – 4, 2010
Europe/Zurich timezone
<span style="color:red"> "Deadline for Proceedings contributions: 20 July 2010" </span>

Modern g,d,p,n-Induced Activation-Transmutation Systems

Jun 4, 2010, 10:00 AM
6-2-024 (BE Auditorium Meyrin) (CERN)

6-2-024 (BE Auditorium Meyrin)


Geneva 23 CH-1211 Geneva Switzerland
Present status of data and code libraries Session 6 - Present status of data and code libraries


Dr Jean-Christophe Sublet (Culham Centre for Fusion Energy)


The European Activation System (EASY) includes as the source of nuclear data the European Activation File (EAF) and as its engine the FISPACT activation-transmutation code. The latest version of the EAF, EAF-2010, contains cross section data for gamma-, deuteron- and proton-induced reactions in addition to the traditional neutron-induced data. The main reason for the addition of these data to EAF is to enable activation-transmutation calculations to be performed for even more nuclear facilities, including ‘accelerator’ driven devices with incident upper energy limit of 60 or 200 MeV. EAF-2010 has benefited from the generation and maintenance of comprehensive activation files in the past and the development of the processing code SAFEPAQ-II and model code TALYS. TALYS is the source for all gamma, proton and deuteron induced data and a fair share of the neutron-induced data. Cross section validation exercises against both experimental data and systematics, which were started in 1995, enable a comprehensive assessment of the data. Although EAF-2010 is certainly the most-validated activation neutron cross section library in the world, currently less than 3% of all the reactions can be compared with experimental information, and even then only for a very limited, and not always application-relevant, energy range. As with EAF-2001, -2003 2005 and 2007 results of integral experiments have been used to correct, adjust and validate data. This can be done using SAFEPAQ-II by inputting the measured effective cross sections. Validation using integral data has been performed by means of direct comparison with measurements of various materials under relevant particle spectra. A tool has recently been developed which is important now that the libraries contain so much TALYS-calculated data. Statistical Analysis of Cross Sections (SACS) is used to look for trends in the library data for a particular reaction type and this has proved efficient in identifying reactions with data that need correction or improvement. This method has been used with EAF-2005 and EAF-2007 and is a valuable additional validation method. However, the time has come to rethink the nuclear data generation processes alongside the transport-activation-transmutation code systems. A new approach is proposed that encompasses 25 years of research activities which can now be mobilised to fulfil the needs, using a much more systematic and automated approach. For the first time, all existing experimental data and nuclear models for all relevant materials can together be transferred to technology in a consistent manner. In this process, feedback of extensive validation and benchmark activities would automatically be taken into account.

Primary author

Dr Jean-Christophe Sublet (Culham Centre for Fusion Energy)


Dr Arjan Koning (Nuclear Research and Consultancy Group (NRG)) Dr Dimitri Rochman (Nuclear Research and Consultancy Group (NRG)) Dr Jura Kopecky (JUKO Research) Dr Lee Packer (Culham Centre for Fusion Energy)

Presentation materials