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Tritium Balance in Large Helical Device during and after the First Deuterium Plasma Experiment Campaign
http://hdl.handle.net/10655/00013003
http://hdl.handle.net/10655/000130038f161437-bb5a-4325-a97d-b5bc00cefa7d
名前 / ファイル | ライセンス | アクション |
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pfr2020_15-1405062 (816.3 kB)
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Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2022-02-09 | |||||
タイトル | ||||||
タイトル | Tritium Balance in Large Helical Device during and after the First Deuterium Plasma Experiment Campaign | |||||
言語 | ||||||
言語 | jpn | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Large Helical 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 | vacuum vessel ventilation | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | tritium inventory | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | tritium balance | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | tritium release behavior | |||||
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× SUZUKI, Naoyuki× MASUZAKI, Suguru× YAJIMA, Miyuki× NAKADA, Miki× IWATA, Chie |
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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 Large Helical Device (LHD) started the deuterium plasma experiment on March 7, 2017. Approximately 6.4 GBq of tritium was produced in the first deuterium plasma experiment campaign and were utilized as tracers for the investigation of release behavior and the balance of tritium in the LHD vacuum vessel. To determine the tritium balance in LHD, the tritium release from the vacuum vessel was continually observed during the plasma experiment period and the vacuum vessel maintenance activities. The tritium exhaust rate was approximately 32.8% at the end of the plasma experiment. After the plasma experiment, the vacuum vessel was ventilated by room air for the maintenance activity and the tritium release from the in-vessel components was observed. The tritium release rate gradually decreased and became constant after four-month in spite of water vapor concentration. It is suggested that the tritium release mechanism from the vacuum vessel is a diffusion-limited process from the bulk. The tritium release amount during the maintenance activity for one year was approximately 5.0%. Considering the decrease of tritium decay for 1.5 years, tritium inventory in LHD was estimated to be approximately 3.66 GBq (57.2%) at the end of maintenance activity. | |||||
書誌情報 |
Plasma and Fusion Research 巻 15, p. 1405062, 発行日 2020-08-19 |
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出版者 | ||||||
出版者 | The Japan Society of Plasma Science and Nuclear Fusion Research | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 1880-6821 | |||||
書誌レコードID | ||||||
収録物識別子タイプ | NCID | |||||
収録物識別子 | AA12346675 | |||||
DOI | ||||||
関連タイプ | isIdenticalTo | |||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1585/pfr.15.1405062 | |||||
権利 | ||||||
権利情報 | (c) 2020 The Japan Society of Plasma Science and Nuclear Fusion Research | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1585/pfr.15.1405062 | |||||
関連名称 | Publisher version | |||||
著者版フラグ | ||||||
出版タイプ | VoR | |||||
出版タイプResource | http://purl.org/coar/version/c_970fb48d4fbd8a85 | |||||
NAIS | ||||||
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