Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors

Hideaki Matsuura, Ryo Okamoto, Yuki Koga, Takuro Suganuma, Kazunari Katayama, Teppei Otsuka, Minoru Goto, Shigeaki Nakagawa, Etsuo Ishitsuka, Kenji Tobita

Research output: Contribution to journalArticle

Abstract

Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption speed of Zr in a Li-loading rod for the reactor operation is experimentally measured, and an analysis model is presented to evaluate the tritium outflow from the Li rod in a high-temperature engineering test reactor (HTTR). On the basis of the presented model, the structure of the Li-loading rod for the demonstration test using the HTTR is proposed.

Original languageEnglish
JournalFusion Engineering and Design
DOIs
Publication statusPublished - Jan 1 2019

All Science Journal Classification (ASJC) codes

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

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