New approaches for MOX multi-recycling

Conference · Mon Jul 01 04:00:00 EDT 2013

OSTI ID:22257900

Gain, T.; Bouvier, E.; Grosman, R.; Senentz, G. H.; Lelievre, F.; Bailly, F.; Brueziere, J. ^[1]; Murray, P. ^[2]

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1. AREVA NC, 1 place Jean Millier, Paris La Defense, 92084 (France)
2. AREVA Federal Services LLC, 4800 Hampden Lane, Bethesda, MD 20814 (United States)

Due to its low fissile content after irradiation, Pu from used MOX fuel is considered by some as not recyclable in LWR (Light Water Reactors). The point of this paper is hence to go back to those statements and provide a new analysis based on AREVA extended experience in the fields of fissile and fertile material management and optimized waste management. This is done using the current US fuel inventory as a case study. MOX Multi-recycling in LWRs is a closed cycle scenario where U and Pu management through reprocessing and recycling leads to a significant reduction of the used assemblies to be stored. The recycling of Pu in MOX fuel is moreover a way to maintain the self-protection of the Pu-bearing assemblies. With this scenario, Pu content is also reduced repetitively via a multi-recycling of MOX in LWRs. Simultaneously, {sup 238}Pu content decreases. All along this scenario, HLW (High-Level Radioactive Waste) vitrified canisters are produced and planned for deep geological disposal. Contrary to used fuel, HLW vitrified canisters do not contain proliferation materials. Moreover, the reprocessing of used fuel limits the space needed on current interim storage. With MOX multi-recycling in LWR, Pu isotopy needs to be managed carefully all along the scenario. The early introduction of a limited number of SFRs (Sodium Fast Reactors) can therefore be a real asset for the overall system. A few SFRs would be enough to improve the Pu isotopy from used LWR MOX fuel and provide a Pu-isotopy that could be mixed back with multi-recycled Pu from LWRs, hence increasing the Pu multi-recycling potential in LWRs.

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22257900
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
FAST REACTORS
FERTILE MATERIALS
HIGH-LEVEL RADIOACTIVE WASTES
IRRADIATION
MIXED OXIDE FUELS
PLUTONIUM 238
PROLIFERATION
RECYCLING
REPROCESSING
VITRIFICATION
WASTE STORAGE
WATER COOLED REACTORS
WATER MODERATED REACTORS