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- W2187753498 abstract "As part of the Department of Energy (DOE) Global Nuclear Energy Partnership (GNEP), AREVA formed the International Nuclear Recycling Alliance (INRA) consisting of recognized world-leading companies in the area of used nuclear fuel (UNF) recycling,. The INRA team, consisting of AREVA, Mitsubishi Heavy Industries (MHI), Japan Nuclear Fuel Ltd (JNFL), Batelle Memorial Institute (BMI), URS Washington Division and Babcock and Wilcox (B&W), prepared a pre-conceptual design for an upgradeable engineering-scale recycling plant with a nominal through put of 800 tHM/y. The preconceptual design of this leading-edge facility was based upon the extensive experience of the INRA team in recycling plant design and real world “lessons learned” from actually building, commissioning, and operating recycling facilities in both France and Japan. The conceptual flowsheet, based upon the COEX TM separations process, separates the useful products for recycling into new fuel and sentences all the remaining fission products and minor actinides (MA) to the high level waste, (HLW) for vitrification. The proposed vitrified waste product will be similar to that currently produced in recycling plants in France. This wasteform has been qualified in France by conducting extensive studies and demonstrations. In the US, the qualification of vitrified glass products has been conducted by the US National Laboratories for the Defence Waste Processing Facility (DWPF), the West Valley Demonstration Plant (WVDP), and the Waste Treatment Plant (WTP). The vitrified waste product produced by recycling is sufficiently different from these current wasteforms to warrant additional trials and studies. In this paper we review the differences in the vitrified waste forms previously qualified in the US with that produced from recycling of UNF in France. The lessons learned from qualifying a vitrified waste form in Europe is compared to the current US process for vitrified waste qualification including waste forms, waste loading, and long term alteration models." @default.
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- W2187753498 date "2009-01-01" @default.
- W2187753498 modified "2023-09-26" @default.
- W2187753498 title "Qualification of a Vitrifi ed High Level Waste Product to Support Used Nuclear Fuel Recycling in the US - 9474" @default.
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