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  1. 原著論文

Physics design study of the divertor power handling in 8 m class DEMO reactor

https://repo.qst.go.jp/records/48415
https://repo.qst.go.jp/records/48415
28c9c99a-1e10-4319-afe0-64fcd00a6790
Item type 学術雑誌論文 / Journal Article(1)
公開日 2017-12-21
タイトル
タイトル Physics design study of the divertor power handling in 8 m class 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 Hoshino, Kazuo

× Hoshino, Kazuo

WEKO 486676

Hoshino, Kazuo

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Asakura, Nobuyuki

× Asakura, Nobuyuki

WEKO 486677

Asakura, Nobuyuki

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Tokunaga, Shinsuke

× Tokunaga, Shinsuke

WEKO 486678

Tokunaga, Shinsuke

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Homma, Yuuki

× Homma, Yuuki

WEKO 486679

Homma, Yuuki

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Shimizu, Katsuhiro

× Shimizu, Katsuhiro

WEKO 486680

Shimizu, Katsuhiro

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Sakamoto, Yoshiteru

× Sakamoto, Yoshiteru

WEKO 486681

Sakamoto, Yoshiteru

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Tobita, Kenji

× Tobita, Kenji

WEKO 486682

Tobita, Kenji

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Special, Design Team for Fusion DEMO Joint

× Special, Design Team for Fusion DEMO Joint

WEKO 486683

Special, Design Team for Fusion DEMO Joint

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星野 一生

× 星野 一生

WEKO 486684

en 星野 一生

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朝倉 伸幸

× 朝倉 伸幸

WEKO 486685

en 朝倉 伸幸

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徳永 晋介

× 徳永 晋介

WEKO 486686

en 徳永 晋介

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本間 裕貴

× 本間 裕貴

WEKO 486687

en 本間 裕貴

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清水 勝宏

× 清水 勝宏

WEKO 486688

en 清水 勝宏

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坂本 宜照

× 坂本 宜照

WEKO 486689

en 坂本 宜照

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飛田 健次

× 飛田 健次

WEKO 486690

en 飛田 健次

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抄録
内容記述タイプ Abstract
内容記述 The divertor plasma performance and the power handling are studied for 8 m class DEMO reactor with the fusion power of 1.5 GW. Due to the high impurity radiation power (80% of the exhausted power),the full detachment at the inner target and the partial detachment at the outer target are obtained for a relatively low electron density of 1.8 × 10^19m^−3at the outer mid-plane separatrix. The SONIC simulation shows the target heat load less than 8 MW/m^2, which can be handled by the ITER-like divertor target, for both target. However, at the outer target, the ion temperature is still high which may cause the target erosion. For the divertor power handling and suppression of the target erosion, the divertor design study have to be further proceeded as well as the core plasma design. Dependence of the mid-plane separatrix density and the impurity concentration on the fuel gas puff is also studied. With increasing fuel gas puff rate, the mid-plane separatrix density increases and the Ar impurity concentration at the outer mid-plane decreases to 0.5%.
書誌情報 Fusion Engineering and Design

巻 124, p. 352-355, 発行日 2017-11
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
DOI
識別子タイプ DOI
関連識別子 10.1016/j.fusengdes.2017.03.068
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