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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.
A. Yamawaki, M. Fukumoto, Y. Soga, Y. Ohtsuka, Y. Ueda, K. Ohya
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 1038-1042
Divertors and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9048
Articles are hosted by Taylor and Francis Online.
Since carbon deposition layers in tokamak devices will contain significant amount of tritium, it is important to study its formation mechanism. In this study, tungsten and molybdenum samples with a temperature gradient were irradiated by a mixed ion beam to precisely study temperature dependence of the deposition characteristics. For molybdenum, the temperature of the boundary between "deposition" and "nodeposition" is higher than W. This results roughly agree with the results by the material mixing model proposed by Kriegeretal [K. Krieger. J. Roth. J. of Nucl. Mater. 290-293 (2003) 107.]. Erosion yield of C deposition layer in our experimental conditions was almost equal or less than the yield by Rothmodel [J. Roth, C. Garcia-Rosales, Nucl. Fusion 36 (1996) 1647] for graphite.