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

Research output: Contribution to journalArticle

3 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)587-591
Number of pages5
JournalFusion Engineering and Design
Volume136
DOIs
Publication statusPublished - Nov 2018

All Science Journal Classification (ASJC) codes

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

Fingerprint Dive into the research topics of 'Study on lithium rod test module and irradiation method for tritium production using high temperature gas-cooled reactor'. Together they form a unique fingerprint.

  • Cite this