Experiment of recovery of tritium from Li by Y and design of hot trap

Satoshi Fukada, Yasushi Maeda, Yuuki Edao

Research output: Contribution to journalArticlepeer-review

7 Citations (Scopus)


The recovery of tritium, T, from neutron-irradiated Li by a Y plate was experimentally investigated, and a Y hot trap was designed to remove T from a flowing Li target loop of IFMIF. T generated in Li ranging from 0.01 to O.OSppm in molar fraction was successfully removed by a Y plate at 300-500°C. The ratio of recovered T to generated one increased with temperature and immersion time. HT was the main chemical species of T that was released from Li, while HTO was the main one without Y absorption. SEM-EDX analysis revealed the transfer of not only T but also O originally included in Li as an impurity. Treatment of Y by HF was effective to remove oxides formed on the as-received Y plate and enhanced its hydrogenating rate. Conditions of a Y hot trap designed for the flowing Li target loop of IFMIF are given in the present paper.

Original languageEnglish
Pages (from-to)117-121
Number of pages5
JournalFusion Science and Technology
Issue number1
Publication statusPublished - Jan 1 2008

All Science Journal Classification (ASJC) codes

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


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