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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.
Marie-Louise Pointud, Pierre Chenebault
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 494-500
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31909
Articles are hosted by Taylor and Francis Online.
Radioactive fission gas release from coated particles containing UO2 or (Th-U)O2 fuel kernels was studied by taking into account the following parameters: (a) porosities of kernels and materials surrounding them, (b) irradiation temperature, (c) burrnup, and (d) thermal neutron flux. The main results follow. First, the structure of the kernels is modified during irradiation and, consequently, the mechanism and rate of fission gas release vary. Second, for a dense fuel, released activity results from recoil species ejected by the external surface of the kernel and reemitted from the surrounding porous carbon. Finally, for an initially porous fuel or for a heavily irradiated dense fuel, recoil atoms reemitted from the internal open porosity of the kernel and atoms ejected by knockout give the most important contributions to the release.