NRC-8, EuCheMS International Conference on Nuclear and Radiochemistry

INVITED LECTURE - Solution reactors for production of Mo-99 and Sr-89 (via Kr-89)

18 Sept 2012, 16:10

20m

Como, Italy

Invited Lecture Nuclear fuel cycles, present Gen III+ NPPs, Gen IV and Th based reactors Session 5 - Nuclear fuel cycles, Research Reactors and present NPP (including Gen IV and Th reactors)

Speaker

Dr Vladimir A. Pavshuk (Russian Research Center “Kurchatov Institute”, Russia)

Description

Molybdenum-99 is the most important and widely used medical radionuclide which production in required quantities is possible only by fission products of Uraniun-235. In clinical practice the share of Mo-99 usage reaches approximately 80% of the total amount of radioisotope diagnostic procedures in the world. Strontium-89 is used for oncology and anesthesia and is capable of replacing painkilling drugs. Innovative technologies for production of Мо-99 and Sr-89 using solution reactors have been developed in RRC “Kurchatov Institute”. These technologies reduce the required reactor power by approximately 100 times, decrease amount of radioactive waste and are suitable for low-enriched uranium fuel in comparison with conventional production methods. The technologies have been experimentally proven and refined using 20-kW solution reactor “Argus” where the isotope samples of required quality have been produced. Mo-99 has been extracted from irradiated soluble nuclear fuel by pumping the solution though a sorption column. Accumulation of the isotope occurs during 5-day reactor operation at nominal power while the extraction is done after the reactor shutdown. Sr-89 is obtained from Kr-89 which is evaporated during reactor operation.

The achieved results lead to further plans including development of Мо-99 and Sr-89 production line using 150-kW nuclear reactor.