2012 Progress report on HEU minimization activities in Argentina

An extension of the original CNEA-NNSA DoE contract for the RA-6 reactor core conversion was signed in March 2010 to enhance the final national HEU inventories minimization. Previously, CNEA reserved a small inventory of HEU for further R and D uses in fission chambers, neutronic probes and standards. This minimization comprises all fresh and irradiated HEU remnant inventories coming from fuels and Mo-99 targets fabrication and irradiated HEU-oxides retained in production filters and solutions. Those inventories are being recovered, down-blended into LEU and purified or, in few cases and due to cost benefit considerations, declared wastes. CNEA has a R and D program focused on the development of the fabrication technology of UMo monolithic (Zry-4 cladding) mini-plates to support the qualification activities of the RERTR program. Some monolithic 58% enrichment and LEU 8%Mo and U10%Mo mini-plates and plates were and are being delivered to INL-DoE to be irradiated in the ATR reactor core. Full scale plates will take part of the ALT FUTURE irradiation at the BR II Belgium reactor. CNEA, a worldwide leader on LEU technology for fission radioisotope production is providing Brazil with 1/3 of the national requirements on Mo-99 by weekly deliveries. ANSTO is firmly producing several fission radioisotopes batches by week. During November and December 2011 the production in the new fission Mo-99 facilities of the Atomic Egyptian Agency (AEA) in Inshas Atomic Center, Egypt was demonstrated. To support these activities CNEA is refurbishing in Ezeiza Atomic Center a set of radiochemical cells where the spent LEU based material retained in the filters of the Mo-99 production facility of CNEA along these last 10 years will be separated from wastes, recovered and purified to be re-utilized in this or in other nuclear applications. CNEA is strongly committed to improve the diffusion of LEU target and radiochemical technology for radioisotope production and target and their process optimization. Future plans include: Development of waste separation techniques optimization; Fabrication and delivering to INL to be irradiated in the ATR core of complementary U-8%Mo and U-10%Mo monolithic miniplates and development and fabrication of LEU very high density monolithic and dispersed U-Mo fuel plates with Zr cladding for the FUTUREMONO experiment in the frame of the RERTR program; Optimization of LEU target and radiochemical techniques for radioisotope production and waste separation, recovery and purification of irradiated LEU inventories contained in fission Mo-99 production filters. (authors)