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Estimation of tritium inventory in exhaust detritiation system for fusion test device in the initial tritium recovery operation
http://hdl.handle.net/10655/00012686
http://hdl.handle.net/10655/0001268679df02f2-ab48-4c4f-ad2d-b8a99658f51e
名前 / ファイル | ライセンス | アクション |
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Fusion_Engin.Des.172_pp112808 (1.3 MB)
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Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2021-12-01 | |||||
タイトル | ||||||
タイトル | Estimation of tritium inventory in exhaust detritiation system for fusion test device in the initial tritium recovery operation | |||||
言語 | ||||||
言語 | eng | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Exhaust detritiation system | |||||
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 | Tritium removal | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Tritiated water | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Tritium contamination | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Tritium inventory | |||||
キーワード | ||||||
主題Scheme | Other | |||||
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× Suzuki, Naoyuki× Kato, Hiromi× Chimura, Hiroki |
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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 | As one of the radiation safety issues at nuclear fusion facilities, the development of the tritium handling technique is indispensable. A small amount of tritium is produced by the deuterium plasma experiment in a large fusion test device and is exhausted from the vacuum vessel. From the viewpoint of radiation safety and public acceptance, tritium in the exhaust gas could be recovered by the exhaust detritiation system (EDS). Most of the tritium recovered by EDS is stored in the wastewater tanks as tritiated water. Then they are fractionated into the wastewater containers for delivery to the Japan Radioisotope Association once a year. However, some of the tritiated water would have remained in EDS. The residual tritium would be the issue of the dismantlement of EDS in the future. Thus, the amount of residual tritium in EDS was estimated in the initial tritium recovery operation. Since most of the wastewater containing tritium remains in the storage tanks, the residual wastewater was the main tritium inventory. Also, the tritium in the molecular sieve used in EDS was estimated to be less than 0.1 GBq. Thus, the decontamination of molecular sieves would be preferred when dismantling the EDS. | |||||
書誌情報 |
Fusion Engineering and Design 巻 172, p. 112808, 発行日 2021-08-02 |
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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 | AA10691446 | |||||
DOI | ||||||
関連タイプ | isVersionOf | |||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1016/j.fusengdes.2021.112808 | |||||
権利 | ||||||
権利情報 | © 2021. This manuscript version is made available under the CC-BY-NC-ND 4.0 | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1016/j.fusengdes.2021.112808 | |||||
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 | ||||||
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