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Preliminary Estimation of Tritium Migration for A-FNS Lithium Target System
https://repo.qst.go.jp/records/82147
https://repo.qst.go.jp/records/821477d47fdf2-e97f-4cea-8599-39cdba7b96a3
Item type | 会議発表用資料 / Presentation(1) | |||||
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公開日 | 2021-03-15 | |||||
タイトル | ||||||
タイトル | Preliminary Estimation of Tritium Migration for A-FNS Lithium Target System | |||||
言語 | ||||||
言語 | eng | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_c94f | |||||
資源タイプ | conference object | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
Makoto, Oyaizu
× Makoto, Oyaizu× Masayuki, Ota× Kentaro, Ochiai× Atsushi, Kasugai× Makoto, Oyaizu× Masayuki, Ota× Kentaro, Ochiai× Atsushi, Kasugai |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | In A-FNS, an accelerator-driven fusion-relevant neutron source, a few grams (3.5 g at full power operation) of tritium will be generated every year mainly in lithium target system. Since the generated tritium would migrate out of lithium target system, it is necessary to estimate the tritium migration in and out of the lithium target system for the design of detritiation systems for A-FNS, and therefore, a preliminary estimation is performed in the present study. As the results, it is found that almost all of the generated tritium in lithium target system would be trapped in impurity removal system, while less than 0.5% of that would migrate out. It is also indicated that the amount of tritium that would migrate out of lithium target system would be able to process with the existing techniques so far. | |||||
会議概要(会議名, 開催地, 会期, 主催者等) | ||||||
内容記述タイプ | Other | |||||
内容記述 | Technology of Fusion Energy (TOFE2020) | |||||
発表年月日 | ||||||
日付 | 2020-11-17 | |||||
日付タイプ | Issued |