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

研究成果: ジャーナルへの寄稿学術論文査読

8 被引用数 (Scopus)

抄録

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.

本文言語英語
ページ(範囲)1077-1081
ページ数5
ジャーナルFusion Engineering and Design
146
DOI
出版ステータス出版済み - 2019 9月

フィンガープリント

「Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル