1. Recent results of R&D activities on tritium technologies for ITER and fusion reactors at TPL of JAEA
- Author
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Yamanishi, T., Hayashi, T., Shu, W., Kawamura, Y., Nakamura, H., Iwai, Y., Kobayashi, K., Isobe, K., Arita, T., Hoshi, S., Suzuki, T., and Yamada, M.
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TRITIUM , *RESEARCH & development projects , *FUSION reactors , *LABORATORIES , *NUCLEAR reactors - Abstract
Abstract: At Tritium Process Laboratory (TPL) of Japan Atomic Energy Agency (JAEA), tritium technologies for a fusion reactor have been carried out up to date. The design studies of Air Detrtiation and Vent Detritiation System (ADS/VDS) of ITER have been carried out in JAEA as a contribution of Japan to ITER. For the tritium processing technologies, our efforts have been focused on the R&D of the tritium recovery system of ITER test blanket system. A ceramic proton conductor has been studied as an advanced blanket system. A series of fundamental studies on tritium safety technologies for ITER and for fusion DEMO plants has also been carried out. The main R&D activities in this field are the tritium behavior in a confinement and its barrier materials, monitoring, accountancy, detritiation and decontamination, etc. Especially, for the fundamental studies for a DEMO plants, a part of the studies will be carries out a new facility at Rokkasho in Aomori in the Broader Approach (BA) program in coming 10 years. For this purpose, a design study of the facility at Rokkasho has first been started. [Copyright &y& Elsevier]
- Published
- 2008
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