Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor

Yuki Koga, Hideaki Matsuura, Yuma Ida, Ryo Okamoto, Kazunari Katayama, Teppei Otsuka, Minoru Goto, Shigeaki Nakagawa, Satoru Nagasumi, Etsuo Ishitsuka, Yosuke Shimazaki

研究成果: Contribution to journalArticle

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Large quantities of tritium are required to start up fusion reactors and conducts engineering tests using tritium for a fusion blanket system. However, tritium is very rare and kg orders of tritium must be produced artificially. Tritium production, by 6Li(n,α)T reaction using a high temperature gas-cooled reactor (HTGR) has been proposed. This method considers the loading of Li rods into burnable poison holes in the HTGR. In this paper, the Li rod suited for use in the High Temperature engineering Test Reactor (HTTR) was designed, and tritium production and leakage from Li-rod capsules were evaluated by adjusting the thicknesses of LiAlO2, alumina, and Zr layers. An irradiation test scenario to be conducted in the HTTR for demonstration of the Li rod's tritium production and containment performance was presented.

元の言語英語
ページ(範囲)587-591
ページ数5
ジャーナルFusion Engineering and Design
136
DOI
出版物ステータス出版済み - 11 2018

All Science Journal Classification (ASJC) codes

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

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