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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.
U. Benedict, G. Giacchetti, Hj. Matzke, K. Richter, C. Sari, H. E. Schmidt
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 154-161
Technical Paper | Fuel | doi.org/10.13182/NT77-A31858
Articles are hosted by Taylor and Francis Online.
Carbide-based fuels simulating high burnup were prepared by addition of inactive fission product elements. They contained fission product phases of the UMoC2 and U2RUC2 type, and a rare-earth oxide phase. The thermal conductivity of the material is within the range observed for carbide-based fuels free of fission products. The diffusion of plutonium was considerably enhanced by the addition of fission products. The solid fission product swelling rate of a carbide-based fuel was estimated to be 0.5% per at.% burnup.