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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.
Suddhasattwa Ghosh, B. Prabhakara Reddy, K. Nagarajan, P. R. Vasudeva Rao
Nuclear Technology | Volume 170 | Number 3 | June 2010 | Pages 430-443
Technical Paper | Reprocessing | doi.org/10.13182/NT10-A10329
Articles are hosted by Taylor and Francis Online.
The computer code PRAGAMAN has been developed for numerical simulation of electrotransport during molten salt electrorefining of spent metallic fuels. The code is based on the thermodynamic equilibriums among pairs of elements and their chlorides that exist at the anode-electrolyte salt and cathode-electrolyte salt interfaces. It uses nonlinear and linear equations to arrive at real solutions for all 16 possible conditions that could be envisaged with respect to the solubilities of U and Pu at the anode and cathode. It can handle the electrotransport of eight elements representing typical actinides, minor actinides, and fission products, as well as potential dependent electrotransport of U and Pu.