| アイテムタイプ |
学術雑誌論文 / Journal Article(1) |
| 公開日 |
2025-04-21 |
| タイトル |
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タイトル |
T production using a high-temperature gas-cooled reactor for the DEMO fusion reactor: Li rod structure for the initial irradiation test |
|
言語 |
en |
| 言語 |
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|
言語 |
eng |
| 資源タイプ |
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資源タイプ識別子 |
http://purl.org/coar/resource_type/c_6501 |
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資源タイプ |
journal article |
| 著者 |
Hideaki Matsuura
Taisei Abe
Motomasa Naoi
Hiromi Kawai
Kazunari Katayama
Teppei Otsuka
Minoru Goto
Shigeaki Nakagawa
Etsuo Ishitsuka
Shimpei Hamamoto
Kenji Tobita
Satoshi Konishi
yuki koga
ryoji hiwatari
youji someya
yoshiteru sakamoto
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| 抄録 |
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内容記述タイプ |
Abstract |
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内容記述 |
This work proposes tritium (T) production using a high-temperature gas-cooled reactor (HTGR) and studies it for the initial T inventory in a demonstration fusion reactor and a prior engineering test with T handling. At this stage, the aim is to investigate the compatibility between electricity and T production, which makes the stable confinement of T in the Li-loading rods during the HTGR operation period a crucial issue. The total T outflow into the helium gas during the reactor operation period was attempted to be reduced using Zr spheres with Ni coating as a T absorption material to avoid an increase in the inner T pressure. The basic hydrogen absorption properties of the Zr spheres with Ni coating, which coexist in an environment with Al2O3 and/or LiAlO2 oxides, were measured. The structures of the Li-loading rod for a typical commercial HTGR and irradiation test were studied using the obtained data. In addition, an outline of the irradiation test is reported. |
| 書誌情報 |
fusion engineering and design
巻 197,
p. 114054,
発行日 2023-11
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| 出版者 |
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出版者 |
Elsevier B.V. |
| ISSN |
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収録物識別子タイプ |
ISSN |
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収録物識別子 |
0920-3796 |
| DOI |
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識別子タイプ |
DOI |
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関連識別子 |
10.1016/j.fusengdes.2023.114054 |
