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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.
J. Miyazawa, S. Masuzaki, R. Sakamoto, B. J. Peterson, N. Tamura, M. Goto, M. Kobayashi, M. Shoji, T. Akiyama, H. Yamada, LHD Experiment Group
Fusion Science and Technology | Volume 58 | Number 1 | July-August 2010 | Pages 200-207
Chapter 5. Divertor and Edge Physics | Special Issue on Large Helical Device (LHD) | doi.org/10.13182/FST10-A10807
Articles are hosted by Taylor and Francis Online.
Easy access to the high-density regime without fatal disruptive phenomena is one of the important characteristics of the Large Helical Device (LHD). The operational density is considerably higher than the Greenwald density limit for tokamak plasmas. The density limit in LHD is reached when the edge density at the last closed flux surface exceeds a value approximately equivalent to the Sudo density limit that increases with the square root of the heating power. Extremely high central density of >1 × 1021 m-3 is achievable with a peaked density profile, as long as the edge density is kept lower than the Sudo limit. Furthermore, the central heating power must be larger than the radiation loss in the core region to avoid the "cold-core" phenomenon. As for the plasma edge, complete detachment takes place when the edge density exceeds the limit. Then, reattachment/Serpens mode/radiative collapse will follow, depending on the recycling condition.