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UID:MEC-aaf662be6cd123f4c54c4d90d24b1373@bnsorg.be
DTSTART:20250424T163000Z
DTEND:20250424T183000Z
DTSTAMP:20250225T160500Z
CREATED:20250225
LAST-MODIFIED:20250513
PRIORITY:5
TRANSP:OPAQUE
SUMMARY:Mox Fuel For Fast Reactors : high level of flexibility towards plutonium management and minor actinide transmutation
DESCRIPTION:All Within the GENERATION IV initiative, several reactors have been selected : sodium fast reactor SFR, lead or lead-bismuth fast reactor LFR, advanced driver system ADS, gas fast reactor GFR, very high temperature reactor VHTR and molten salt reactor MSR. Innovative fuels have been selected especially for the fast neutron reactor (SFR, LFR and GFR) : it’s ceramics like oxide mixed (U,Pu)O2 or mixed nitride (U,Pu)N or mixed carbide (UPu)C and also metal fuel UPuZr.\nThere is a long experience on fast reactors since the 50’s, of using oxide fuel. Now the Fast reactors in operation are mainly loaded with oxide fuel : in Russia with BOR60, BN600, BN800, in Japan with JOYO, in India with FBTR and in China with CEFR and CFR600.\nThe performances for the evaluation are focused on the capability to reach high burn-up and the flexibility towards various operating conditions : this means for example the ability to operate at lower power or lower temperature ranges.Secondly the behavior in case of transients up to severe accidents are the most important factors to take into consideration.\nCriteria related to the fuel cycle are the cost of fabrication and reprocessing, which will make the difference. In the case of closed fuel cycle, the ability to manage the plutonium and to burn minor actinides  is very important. Fast reactors are flexible towards the cycle and the associated scenarios with different assumptions of the nuclear park. This is the unique system that can offer this. The ability of MOX fuel in FR to burn, to breed or to multirecycle plutonium have been demonstrated. The European project PuMMA has recently provided data towards the impact of Pu management on the whole fuel cycle.\nTowards transmutation of minor actinides and for heterogeneous fuel, with Inert Matrix Fuels  a comprehensive database thank to ~35 experiments have been achieved in MTRs & PHENIX with promising results . Now there is less interest due to transmutation performances reduced. As inert matrices are very difficult to be reprocessed, a once-through strategy is adopted and the transmutation rate in one way remains lowest compared to the performances obtained with homogeneous mode transmutation or minor actinides bearing blankets.\nMinor Actinides Bearing Blanket is  a promising solution but at an early stage of development. Analytical irradiations, fabrication R&D and adapted fuel design should progress in the coming years for a future evaluation. Front end and back end of the fuel cycle are strongly affected by MABB Sub Assembly composition. An adapted and probably innovative design of the fuel Sub-Assembly and of the fuel element should answer to these technological aspects.\nOn the homogeneous mode of transmutation, fuel performances seem to be not affected by americium loading but a full demonstration is still needed with representatives Linear Heat Rate, high burn up and the final fuel element design.\nTiming\n18:30: Introduction of the EVL18:35: Presentation19:25: Q&A19:45: Drink20:30: End\n \n
URL:https://bnsorg.be/event/evening-lecture-april-2025-mox-fuel/
CATEGORIES:Evening Lecture
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