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Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors
https://repo.qst.go.jp/records/77705
https://repo.qst.go.jp/records/77705e31d3953-0427-499f-b0a1-46da26e4efb5
Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2019-11-28 | |||||
タイトル | ||||||
タイトル | Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors | |||||
言語 | ||||||
言語 | eng | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
資源タイプ | journal article | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
Matsuura, Hideaki
× Matsuura, Hideaki× Okamoto, Ryo× Koga, Yuki× Suganuma, Takuro× Katayama, Kazunari× Otsuka, Teppei× Goto, Minoru× Nakagawa, Shigeaki× Ishitsuka, Etsuo× Tobita, Kenji× Kenji, Tobita |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | 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. | |||||
書誌情報 |
Fusion Engineering and Design 巻 146, 号 A, p. 1077-1081, 発行日 2019-09 |
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出版者 | ||||||
出版者 | Elsevier | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 0920-3796 | |||||
DOI | ||||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1016/j.fusengdes.2019.02.009 | |||||
関連サイト | ||||||
識別子タイプ | URI | |||||
関連識別子 | https://www.sciencedirect.com/science/article/pii/S0920379619301814 |