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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/82147
7d47fdf2-e97f-4cea-8599-39cdba7b96a3
Item type 会議発表用資料 / Presentation(1)
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

WEKO 934637

Makoto, Oyaizu

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Masayuki, Ota

× Masayuki, Ota

WEKO 934638

Masayuki, Ota

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Kentaro, Ochiai

× Kentaro, Ochiai

WEKO 934639

Kentaro, Ochiai

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Atsushi, Kasugai

× Atsushi, Kasugai

WEKO 934640

Atsushi, Kasugai

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Makoto, Oyaizu

× Makoto, Oyaizu

WEKO 934641

en Makoto, Oyaizu

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Masayuki, Ota

× Masayuki, Ota

WEKO 934642

en Masayuki, Ota

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Kentaro, Ochiai

× Kentaro, Ochiai

WEKO 934643

en Kentaro, Ochiai

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Atsushi, Kasugai

× Atsushi, Kasugai

WEKO 934644

en 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
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Ver.1 2023-05-15 17:45:48.755306
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