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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.
H. Venker, M. Bober, G. Schumacher
Nuclear Technology | Volume 34 | Number 1 | June 1977 | Pages 98-100
Technical Paper | Fuel | doi.org/10.13182/NT77-A31833
Articles are hosted by Taylor and Francis Online.
In the steep radial temperature gradient existing in the cladding wall of a reactor fuel pin, migration of vacancies up and lattice atoms down the temperature gradient can take place. The transport mechanisms are thermal diffusion and diffusion due to a radial activity gradient of vacancies caused by the temperature-dependent supersaturation of vacancies. An estimation shows that thermal diffusion could contribute to cladding dilatation under fast-neutron irradiation. The enhancement of diffusion under irradiation is derived from in-pile diffusion data of copper and gold in aluminum, because corresponding data of stainless steel are not available.