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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.
Hongyu Bai, Yanfang Bi, Jingrong Wang, Ming Zhuang, Ping Zhu, Linhai Sheng, Qiyong Zhang
Fusion Science and Technology | Volume 42 | Number 1 | July 2002 | Pages 162-166
Technical Paper | doi.org/10.13182/FST02-A224
Articles are hosted by Taylor and Francis Online.
HT-7U is a fully superconducting tokamak. All of the toroidal field and poloidal field superconducting magnets are made of NbTi superconductor and are designed to operate at 3.8 K in the steady-state operation mode. The magnet system will be cooled with forced-flow supercritical helium to this temperature level with an equivalent refrigeration capacity of ~2 kW/4.4 K. To satisfy this requirement, a helium refrigerator is designed to be able to provide the cooling power at 3.5, 4.5, and 80 K for the coils, supports, and thermal shields. The refrigerator can also produce liquid helium for the cooling of the current leads. This paper describes the cryogenic system of HT-7U, the refrigeration process and helium plant, and the forced-flow cooling requirement of the superconducting magnets.