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

Satoshi Fukada, Akio Morisaki, Akio Sagara, Takayuki Terai

Research output: Contribution to journalConference articlepeer-review

15 Citations (Scopus)


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.

Original languageEnglish
Pages (from-to)477-483
Number of pages7
JournalFusion Engineering and Design
Volume81 A
Issue number1-4
Publication statusPublished - Feb 2006
EventProceedings of the Seventh International Symposium on Fusion Nuclear Technology ISFNT-7 Part A -
Duration: May 22 2005May 27 2005

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering


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