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Tritium decontamination in vacuum vessel after deuterium plasma experiment due to air exposure
http://hdl.handle.net/10655/00013609
http://hdl.handle.net/10655/0001360944e48714-b541-459d-bb0d-caf700ae9965
名前 / ファイル | ライセンス | アクション |
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13370_Fusion.Eng.Des (733.8 kB)
Download is available from 2025/3/3.
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Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2023-05-24 | |||||
タイトル | ||||||
タイトル | Tritium decontamination in vacuum vessel after deuterium plasma experiment due to air exposure | |||||
言語 | ||||||
言語 | eng | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Fusion test device | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Deuterium plasma experiment | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Tritium decontamination | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Air exposure | |||||
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
× TANAKA, Masahiro× KATO, Hiromi× CHIMURA, Hiroki× SUZUKI, Naoyuki |
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著者ID | ||||||
内容記述タイプ | Other | |||||
内容記述 | 0000-0001-9941-1958 | |||||
抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The deuterium plasma experiment using Large Helical Device (LHD) has been conducted since 2017. A small amount of tritium was produced in the vacuum vessel and a part of tritium remained in the plasma-facing materials. After the deuterium plasma experimental campaign, the vacuum vessel was opened for the LHD maintenance activity. Then, the plasma-facing material was exposed to room air and remained tritium was released at ambient temperature. The tritium release rate increased rapidly immediately after the vacuum vessel was opened to the atmosphere, but it turned to decrease soon after. After several weeks of opening the vacuum vessel, the tritium release rate became low and almost constant. The total tritium decontamination rate, defined as the ratio of tritium released by air exposure to tritium produced during the plasma experimental campaign, was achieved at several percent. The air exposure operation is expected to have a decontamination effect due to isotope exchange reactions on the surface of the plasma-facing material. | |||||
書誌情報 |
Fusion Engineering and Design 巻 192, 号 July 2023, p. 113628, 発行日 2023-03-04 |
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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 | |||||
書誌レコードID | ||||||
収録物識別子タイプ | NCID | |||||
収録物識別子 | AA11529170 | |||||
DOI | ||||||
関連タイプ | isVersionOf | |||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1016/j.fusengdes.2023.113628 | |||||
権利 | ||||||
権利情報 | © 2023 Elsevier B.V. | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1016/j.fusengdes.2023.113628 | |||||
関連名称 | publisher version | |||||
著者版フラグ | ||||||
出版タイプ | AM | |||||
出版タイプResource | http://purl.org/coar/version/c_ab4af688f83e57aa | |||||
NAIS | ||||||
13370 |