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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
E. G. Samsel, J. R. Berreth
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 68-75
Technical Paper | Radioactive Waste | doi.org/10.13182/NT77-A31764
Articles are hosted by Taylor and Francis Online.
Simulated high-level commercial fluidized-bed calcine was treated to form sintered glass-ceramics (SGC) by sintering compacted mixtures of calcine with aluminosilicate fluxes at temperatures ranging from 965 to 1070°C. Products are resistant to impact and thermal shock and exhibit leach rates of 10−5 to 10−9 g/(cm2 day). Up to 67 wt% calcine is used, giving waste volumes as low as 0.040 m3 /MTU reprocessed. Storage centerline temperatures up to 800°C appear feasible. A conceptual process in which SGC is molded into thin-walled containers for processing and canister loading is proposed.