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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.
T. Kinjyo, M. Nishikawa, N. Yamashita, T. Koyama, K. Suematsu, S. Fukada, M. Enoeda
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 557-560
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1877
Articles are hosted by Taylor and Francis Online.
A tritium release model has been developed by the present authors. The tritium release curves estimated by this tritium model give good agreement with experimental curves for Li4SiO4, Li2TiO3, Li2ZrO3 or LiAlO2 under various purge gas conditions in our out-of-pile bred tritium release.The characteristics of tritium release behavior from various solid breeder materials carried out by us and in EXOTIC experiments at Petten are discussed in this study.