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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.
R. W. Schaefer, R. M. Lell, R. D. McKnight
Nuclear Science and Engineering | Volume 145 | Number 1 | September 2003 | Pages 84-96
Technical Paper | doi.org/10.13182/NSE03-A2365
Articles are hosted by Taylor and Francis Online.
Numerous criticality safety benchmarks have been, and continue to be, developed from experiments performed on Argonne National Laboratory's plate-type fast critical assemblies. The nature and scope of assemblies suitable for deriving these benchmarks are discussed. The benchmark derivation process, including full treatment of all significant uncertainties, is explained. Calculational results are presented that support the small uncertainty assigned to the key derivation step in which complex geometric detail is removed.