Control of tritium in FFHR-2 self-cooled Flibe blanket

Satoshi Fukada, Akio Morisaki, Akio Sagara, Takayuki Terai

研究成果: Contribution to journalConference article

14 引用 (Scopus)

抜粋

The application of Flibe (2LiF + BeF2 mixed molten salt) to a blanket material of force-free helical reactor (FFHR-2) was discussed based on our recent experiments on redox control of Flibe by Be and on hydrogen permeation through Flinak (0.465LiF + 0.115NaF + 0.42 KF mixed molten salt) as a fluid simulant of Flibe. The two experimental works were carried out under the collaboration work of JUPITER-II. To maintain Flibe in the blanket loop under reduction condition is a key issue to transform TF to T2 with a fast reaction rate. In order to achieve that, proper rates of Be dissolution and reduction reaction of TF to T2 in Flibe have to be established in the self-cooled blanket. The overall material balance of tritium in the FFHR-2 system was discussed in terms of the tritium permeation through Flibe and the tritium recovery rate.

元の言語英語
ページ(範囲)477-483
ページ数7
ジャーナルFusion Engineering and Design
81 A
発行部数1-4
DOI
出版物ステータス出版済み - 2 1 2006
イベントProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A -
継続期間: 5 22 20055 27 2005

All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering

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