Hydrogen permeation through Flinabe fluoride molten salts for blanket candidates

Ryosuke Nishiumi, Satoshi Fukada, Akira Nakamura, Kazunari Katayama

Research output: Contribution to journalArticlepeer-review

7 Citations (Scopus)


Fluoride molten salt Flibe (2LiF + BeF2) is a promising candidate for the liquid blanket of a nuclear fusion reactor, because of its large advantages of tritium breeding ratio and heat-transfer fluid. Since its melting point is higher than other liquid candidates, another new fluoride molten salt Flinabe (LiF + NaF + BeF2) is recently focused on because of its lower melting point while holding proper breeding properties. In this experiment, hydrogen permeation behavior through the three molten salts of Flibe (2LiF + BeF2), Fnabe (NaF + BeF2) and Flinabe are investigated in order to clarify the effects of their compositions on hydrogen transfer properties. After making up any of the three molten salts and purifying it using HF, hydrogen permeability, diffusivity and solubility of the molten salts are determined experimentally by using a system composed of tertiary cylindrical tubes. Close agreement is obtained between experimental data and analytical solutions. H2 permeability, diffusivity and solubility are correlated as a function of temperature and are compared among the three molten salts.

Original languageEnglish
Pages (from-to)1663-1668
Number of pages6
JournalFusion Engineering and Design
Publication statusPublished - 2016

All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • General Materials Science
  • Mechanical Engineering


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