| Item type |
学術雑誌論文 / Journal Article(1) |
| 公開日 |
2025-02-04 |
| タイトル |
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タイトル |
Determination of tritium inventory in carbon divertor tiles used in deuterium plasma experiment by induction heating method |
|
言語 |
en |
| 言語 |
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|
言語 |
eng |
| キーワード |
|
|
言語 |
en |
|
主題Scheme |
Other |
|
主題 |
Tritium inventory |
| キーワード |
|
|
言語 |
en |
|
主題Scheme |
Other |
|
主題 |
Carbon divertor tile |
| キーワード |
|
|
言語 |
en |
|
主題Scheme |
Other |
|
主題 |
Tritium chemical forms |
| キーワード |
|
|
言語 |
en |
|
主題Scheme |
Other |
|
主題 |
Deuterium plasma experiment |
| キーワード |
|
|
言語 |
en |
|
主題Scheme |
Other |
|
主題 |
Thermal desorption |
| キーワード |
|
|
言語 |
en |
|
主題Scheme |
Other |
|
主題 |
Induction heating method |
| 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 |
| 著者 |
TANAKA, Masahiro
KATO, Hiromi
SUZUKI, Naoyuki
CHIMURA, Hiroki
YONEZU, Hiroaki
MASUZAKI, Suguru
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| 著者ID |
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内容記述タイプ |
Other |
|
内容記述 |
ORCID 0000-0001-9941-1958 |
| 抄録 |
|
|
内容記述タイプ |
Abstract |
|
内容記述 |
The tritium inventory of the plasma-facing materials in a Large Helical Device (LHD) was analyzed using a thermal desorption system. In this study, we developed an induction heating system for the thermal desorption of tritium from carbon divertor tiles, which has several advantages, including a rapid temperature rise, internal heating via eddy currents, and heating with the original size and shape of the carbon tile. The apparatus was capable of heating a carbon divertor tile to a temperature greater than 1373 K over 20 min. Following a 12-h heating period at 1423 K, the tritium release rate from the carbon tile was 99.7 %. The chemical form of the tritium released from the divertor tiles was approximately 80 % molecular hydrogen, with the remaining tritium in the form of water vapor. The results of the tritium analysis of the divertor tiles suggest that the tritium distribution in the divertor region is not uniform, and that the flux varies from location to location in the LHD. To improve the accuracy of the tritium inventory analysis in an LHD vacuum vessel, it is essential to conduct a tritium inventory analysis of other plasma-facing materials. |
|
言語 |
en |
| bibliographic_information |
en : Nuclear Materials and Energy
巻 42,
号 March 2025,
p. 101876,
発行日 2025-01-18
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| item_10001_text_25 |
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en |
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This article is part of a special issue entitled: ‘PSI-26’ published in Nuclear Materials and Energy. |
| 出版者 |
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出版者 |
Elsevier |
|
言語 |
en |
| item_10001_source_id_9 |
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収録物識別子タイプ |
EISSN |
|
収録物識別子 |
2352-1791 |
| item_10001_relation_14 |
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|
関連タイプ |
isIdenticalTo |
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識別子タイプ |
DOI |
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関連識別子 |
https://doi.org/10.1016/j.nme.2025.101876 |
| 権利 |
|
|
言語 |
en |
|
権利情報 |
© 2025 The Authors. |
| 関連サイト |
|
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|
識別子タイプ |
DOI |
|
|
関連識別子 |
https://doi.org/10.1016/j.nme.2025.101876 |
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|
関連名称 |
Publisher version |
| 出版タイプ |
|
|
出版タイプ |
VoR |
|
出版タイプResource |
http://purl.org/coar/version/c_970fb48d4fbd8a85 |
| item_10001_text_23 |
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14206 |
14206_Nucl.Mat.Eng.pdf (3.7 MB)
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