Hydrogen permeation behavior through F82H at high temperature

Shohei Matsuda, Kazunari Katayama, Motoki Shimozori, Satoshi Fukada, Hiroki Ushida, Masabumi Nishikawa

Research output: Contribution to journalArticlepeer-review

6 Citations (Scopus)


F82H is a primary candidate of structural material and coolant pipe material in a blanket of a fusion reactor. Understanding tritium permeation behavior through F82H is important. In a normal operation of a fusion reactor, the temperature of F82H will be controlled below 550 °C because it is considered that F82H can be used up to 30,000 hours at 550 °C. However, it is necessary to assume the situation where F82H is heated over 550 °C in a severe accident. In this study, hydrogen permeation behavior through F82H was investigated in the temperature range from 500 °C to 800 °C. In some cases, water vapor was added in a sample gas to investigate an effect of water vapor on hydrogen permeation. The permeability of hydrogen in the temperature range from 500 °C to 700 °C agreed well with the permeability reported by E. Serra et al. The degradation of the permeability by water vapor was not observed. After the hydrogen permeation reached in a steady state at 700 °C, the F82H sample was heated to 800 °C. The permeability of hydrogen through F82H sample which was once heated up to 800 °C was lower than that of the original one.

Original languageEnglish
Pages (from-to)467-470
Number of pages4
JournalFusion Science and Technology
Issue number2
Publication statusPublished - Mar 1 2015

All Science Journal Classification (ASJC) codes

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


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