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  1. 原著論文

Shutdown dose-rate assessment during the replacement of in-vessel components for a fusion DEMO reactor

https://repo.qst.go.jp/records/48891
https://repo.qst.go.jp/records/48891
06201383-0a9a-48cf-bc10-3677a53be9ca
Item type 学術雑誌論文 / Journal Article(1)
公開日 2018-05-08
タイトル
タイトル Shutdown dose-rate assessment during the replacement of in-vessel components for a fusion DEMO reactor
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_6501
資源タイプ journal article
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 染谷, 洋二

× 染谷, 洋二

WEKO 492541

染谷, 洋二

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宇藤, 裕康

× 宇藤, 裕康

WEKO 492542

宇藤, 裕康

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日渡, 良爾

× 日渡, 良爾

WEKO 492543

日渡, 良爾

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谷川, 尚

× 谷川, 尚

WEKO 492544

谷川, 尚

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飛田, 健次

× 飛田, 健次

WEKO 492545

飛田, 健次

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Special, Design Team for Fusion Joint

× Special, Design Team for Fusion Joint

WEKO 492546

Special, Design Team for Fusion Joint

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染谷 洋二

× 染谷 洋二

WEKO 492547

en 染谷 洋二

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宇藤 裕康

× 宇藤 裕康

WEKO 492548

en 宇藤 裕康

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日渡 良爾

× 日渡 良爾

WEKO 492549

en 日渡 良爾

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谷川 尚

× 谷川 尚

WEKO 492550

en 谷川 尚

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飛田 健次

× 飛田 健次

WEKO 492551

en 飛田 健次

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抄録
内容記述タイプ Abstract
内容記述 The shutdown dose rate at Japan’s demonstration nuclear fusion (DEMO) plant was analyzed using MCNP-5 and DCHAIN-SP2001 to assess its significance in the development of a maintenance program. It was assumed that the blanket segments were integrated with a shielding plug (SP) and replaced through vertical upper ports, whereas divertor cassettes, also integrated with the SP, were replaced through bottom ports. To minimize the dose rate, remote handling equipment should approach from behind the SP and be fixed with an attachment to it. The estimated dose rates during manifold cutting and rewelding in the maintenance ports were as low as 0.01 Gy/h for the blanket segment and 0.1 Gy/h for the divertor cassette. When the outboard blanket segments and divertor cassettes were removed along with the SP, a spatial dose rate of 100 Gy/h was found at the maintenance ports. The spatial dose rate of the in-vacuum vessel at ITER during maintenance using remote handling equipment is limited to 250 Gy/h. The study confirmed that a maintenance scheme involving pipe cutting or rewelding would be applicable to ITER at the estimated spatial dose rates.
書誌情報 Fusion Engineering and Design

巻 124, p. 615-618, 発行日 2018-05
出版者
出版者 Elsevier
DOI
識別子タイプ DOI
関連識別子 10.1016/j.fusengdes.2017.02.108
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