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Tanigawa, Hisashi; Yoshikawa, Akira; Enoeda, Mikio
no journal, ,
In the design of a test blanket module (TBM) being developed by JAEA, the partial pressure of tritium is controlled to be about 1 Pa using helium purge gas. The tritium diffusion coefficient in F82H steel is an important parameter for the permeation calculation. The permeation behaviour of deuterium affected by the oxide layer was observed by the in-situ experiment. In addition, it was found that hydrogen caused by the oxidative reaction can permeate through the tube. Using the apparent diffusion coefficient obtained in the study, tritium permeation in the TBM is estimated.
Enoeda, Mikio; Suzuki, Satoshi; Tsuru, Daigo; Hirose, Takanori; Tanigawa, Hisashi; Seki, Yohji; Ezato, Koichiro; Yokoyama, Kenji; Nishi, Hiroshi; Dairaku, Masayuki; et al.
no journal, ,
As the primary candidate of ITER Test Blanket Module (TBM) for the first day of ITER operation, development of Water Cooled Solid Breeder (WCSB) TBM has been performed toward the TBM milestones, which are necessary for acceptance of the TBM in ITER for testing from the first day of plasma operation. Milestones of ITER TBMs prior to the installation consist of milestones on safety assessment, module qualification and design integration in ITER. This paper overviews the recent achievements for preparation of the WCSB TBM for ITER day-1 operation, toward the TBM milestones.
Seki, Yohji; Hirose, Takanori; Yoshikawa, Akira; Enoeda, Mikio; Fukada, Satoshi*; Nishikawa, Masabumi*; Kinjo, Tomohiro*
no journal, ,
no abstracts in English