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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.
Y. Uchida, K. Katayama, T. Okamura, R. Imaoka, M. Nishikawa, S. Fukada
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 545-548
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1874
Articles are hosted by Taylor and Francis Online.
From the viewpoints of plasma control and radiation safety, tritium retention in deposition layers is an important problem. In this study, deposition layers from type 316 stainless steel were formed by a sputtering method using hydrogen RF plasma at three different temperatures. The behavior of hydrogen release from the deposition layers was observed by a thermal desorption method at argon atmosphere. It was found that hydrogen retention and release behavior greatly change depending on the temperature of a substrate where the layer is formed. The surface structure of the layer also changed depending on the temperature. However, the ratios of metallic atoms such as Fe, Cr and Ni in deposition layers were almost the same as that in type 316 stainless steel