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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.
Aligati Venkatesh, Suddhasattwa Ghosh, S. Vandarkuzhali, B. Prabhakara Reddy, K. Nagarajan, P. R. Vasudeva Rao
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 98-110
Technical Paper | Reprocessing | doi.org/10.13182/NT182-98
Articles are hosted by Taylor and Francis Online.
The DIFfusion of Actinides in EleCtrorefiner (DIFAC) computer code has been developed and is used to calculate the variation of the anode potential with time during constant current anodic dissolution of U, Zr, and U-Zr alloy in molten LiCl-KCl eutectic. A few algorithms are proposed within the framework of the DIFAC code for modeling the activation and concentration overpotentials during anodic dissolution. These algorithms are based on an iterative search procedure and would later be applied to modeling the electrorefining of a multicomponent metallic fuel system.