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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.
Shinichi Kitawaki, Akira Nakayoshi, Mineo Fukushima, Noboru Yahagi, Masaki Kurata
Nuclear Technology | Volume 171 | Number 3 | September 2010 | Pages 285-291
Technical Paper | Pyro 08 Special / Reprocessing | doi.org/10.13182/NT10-A10863
Articles are hosted by Taylor and Francis Online.
Various residues containing uranium and transuranic are considered to be generated in pyroprocessing, and provided that the actinide elements are recovered from the residues, this can contribute to increasing the recovery ratio in the entire process. In this study the chemical form of the anode residues generated in our previous electrolysis test was investigated. The anode residue consisted of PuOCl, PuO2, and UO when electrolysis was performed using reduced oxide fuels, which are thought to be formed by the reaction between the anode residue and U-chloride contained in the molten salt. By adding ZrCl4 the actinide contained in the residue was converted to chloride. The chlorination reaction took [approximately]10 h to complete.