Removal rates of hydrogen isotope from liquid Li by HF-treated Y plate

Y. Wu, Y. Edao, S. Fukada, H. Nakamura, H. Kondo

Research output: Contribution to journalArticlepeer-review

4 Citations (Scopus)


The International Fusion Materials Irradiation Facility (IFMIF) is designed to provide an intense neutron source for the development of fusion reactor materials. Neutron is supplied by the D-7Li reaction, and at the same time tritium (T) is generated as its by-product. Therefore, the removal of T generated in Li becomes inevitable. It is proved in the present study that HF pretreatment of Y getter materials leads to enhance hydrogenating rates of Y placed in Li. The ratio of the H removal rate of HF-treated Y to that of non-treated Y is determined under the conditions of three different temperatures of 573K, 553K and 523K. The effect of enhancement of hydrogenating rates is quantitatively determined.

Original languageEnglish
Pages (from-to)1484-1487
Number of pages4
JournalFusion Engineering and Design
Issue number7-9
Publication statusPublished - Dec 2010

All Science Journal Classification (ASJC) codes

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


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