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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. Martin et al.
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 65-69
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8877
Articles are hosted by Taylor and Francis Online.
The main function of the ITER divertor system is to exhaust the major part of the alpha particle power as well as helium and impurities from the plasma. In order to fulfil these functions a divertor, a cooling system, a high vacuum pumping system , diagnostics and a gas injection system need to be integrated into the lower part of the vacuum vessel and into the divertor level ports. All components need to be assembled/disassembled using RH tools. The integration of all these systems has been undertaken to ensure that the overall functionality of the divertor is preserved, while fulfilling the requirements of each specific system.