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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.
W. P. Barthold, J. C. Beitel
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 44-60
Technical Paper | Reactor | doi.org/10.13182/NT79-A32237
Articles are hosted by Taylor and Francis Online.
Six homogeneous and heterogeneous core configurations with different fuel pin diameters and different degrees of neutronic coupling have been analyzed. All designs were based on the same design assumptions and constraints. Homogeneous and heterogeneous designs were evaluated with respect to fissile inventory, flux and power distribution, burnup, breeding ratio and doubling times, sodium void reactivity, Doppler coefficient, control rod worth, and transient response. The sensitivity of breeding performance to different fuel life criteria was determined.