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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.
F. D’Annucci, C. Sari, G. Schumacher
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 80-86
Technical Paper | Reactor | doi.org/10.13182/NT77-A31851
Articles are hosted by Taylor and Francis Online.
The fission-product elements molybdenum and ruthenium were added to uranium and uranium-plutonium oxide by a co-precipitation technique. Heat treatment of these materials in a simulated reactor thermal gradient causes migration and coagulation of the metals to form inclusions up to a maximum size of 10 m. Inclusions of large diameters between 5 and 10 µm do not migrate noticeably by diffusion. Their migration rate is different from that of pores in a temperature gradient.