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GEN IV Webinar Series 49: MOX Fuel for Advanced Reactors, January 28, 2021, 8:30 a.m. - 10:30 a.m. (ET)


Today, knowledge on MOX fuel behavior in fast neutron reactors comes mainly from feedback on SFRs that have operated in the past in Europe, USA, Japan and are still in service in Russia, India and China. The GENERATION-IV systems (SFR, GFR, LFR, FSMR...) with the associated fuel cycle strategy have been chosen to face the requirements of safety, non-proliferation, sustainability and waste minimization. This completion is possible thanks to the flexibility of fast neutron systems: they offer the possibility of using plutonium and uranium coming from spent fuel, making the best use of resources while reducing waste. Thus (U,Pu)O2 has proved to be the most ready candidate to achieve these performances in reactor and during the fuel cycle. Mox fuel is suitable for exemple for multirecycling, isogeneration, burning or breeding plutonium through adjustment of Pu concentration. Taking into account a wide range of fuel composition (Pu content: 20 to 45%), irradiation conditions and applying the safety criteria, we will present the state of the art on MOX fuel for GENIV systems with respect to knowledge and qualification. The knowledge on (U,Pu)O2 will be presented under the aspects of material properties and fuel behavior under irradiation with post irradiation examinations and modelling. The methodology of MOX qualification will be will be detailed with TRL (Technological Readiness Level) scale evaluation and the need to extend the qualification area in order to cover all design, composition and situations described above. The support of the international organizations (GIF, OECD/NEA, IAEA, EURATOM) to scientific and technological issues will be assessed.