Verification to recover tritium in neutron-irradiated Li by Y plate

Satoshi Fukada, Yasushi Maeda, Mika Kinoshita, Takeo Muroga

研究成果: ジャーナルへの寄稿記事

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The recovery of tritium from neutron-irradiated Li by an Y plate was experimentally investigated for tritium removal in a Li loop of IFMIF. The molar fraction of tritium included in neutron-irradiated Li ranges from 0.007 to 0.04 ppm. The Y plate at 400-500 °C successfully recovered the low concentration of tritium dissolved in Li. Although HTO as well as HT remained in Li without T recovery, the main chemical species of tritium remaining in Li after recovery was HT, and HT and HTO was released from Y after T recovery. SEM-EDX analysis revealed the transfer of not only tritium or hydrogen but also oxygen originally included in Li. The treatment of Y by a HF acid solution was effective to remove oxides formed on the Y plate and to enhance its hydrogenating rate.

元の言語英語
ページ(範囲)2152-2157
ページ数6
ジャーナルFusion Engineering and Design
82
発行部数15-24
DOI
出版物ステータス出版済み - 10 1 2007

    フィンガープリント

All Science Journal Classification (ASJC) codes

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

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