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  1. 原著論文

Reduction of poloidal magnetic flux consumption during plasma current ramp-up in DEMO relevant plasma regimes

https://repo.qst.go.jp/records/47757
https://repo.qst.go.jp/records/47757
f4481337-665f-40b6-8bfa-e9de0c23790d
Item type 学術雑誌論文 / Journal Article(1)
公開日 2017-04-25
タイトル
タイトル Reduction of poloidal magnetic flux consumption during plasma current ramp-up in DEMO relevant plasma regimes
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 Wakatsuki, Takuma

× Wakatsuki, Takuma

WEKO 479213

Wakatsuki, Takuma

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鈴木, 隆博

× 鈴木, 隆博

WEKO 479214

鈴木, 隆博

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林, 伸彦

× 林, 伸彦

WEKO 479215

林, 伸彦

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白石, 淳也

× 白石, 淳也

WEKO 479216

白石, 淳也

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坂本, 宜照

× 坂本, 宜照

WEKO 479217

坂本, 宜照

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井手, 俊介

× 井手, 俊介

WEKO 479218

井手, 俊介

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久保, 博孝

× 久保, 博孝

WEKO 479219

久保, 博孝

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鎌田, 裕

× 鎌田, 裕

WEKO 479220

鎌田, 裕

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若月 琢馬

× 若月 琢馬

WEKO 479221

en 若月 琢馬

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鈴木 隆博

× 鈴木 隆博

WEKO 479222

en 鈴木 隆博

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林 伸彦

× 林 伸彦

WEKO 479223

en 林 伸彦

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白石 淳也

× 白石 淳也

WEKO 479224

en 白石 淳也

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坂本 宜照

× 坂本 宜照

WEKO 479225

en 坂本 宜照

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井手 俊介

× 井手 俊介

WEKO 479226

en 井手 俊介

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久保 博孝

× 久保 博孝

WEKO 479227

en 久保 博孝

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鎌田 裕

× 鎌田 裕

WEKO 479228

en 鎌田 裕

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抄録
内容記述タイプ Abstract
内容記述 The method for reducing a magnetic flux consumption of a central
solenoid (CS) is investigated to reduce the size of CS in DEMO reactor. The
reduction of the CS flux consumption during a plasma current ramp-up phase by the electron cyclotron (EC) heating is investigated using an integrated modeling code suite, TOPICS. A strongly reversed shear q profile tend to be produced and the plasma might be disruptive if intense off-axis EC heating is applied. However, we find the optimum temperature profile corresponding to a weak shear q profile with which the resistive flux consumption is minimized. This optimum temperature profile is tried to be reproduced using 6 EC rays with 20 MW and the resistive flux consumption during the current ramp-up can be reduced by 63% from the estimation using the Ejima constant of 0.45. As a result of this reduction, the total flux consumption can be reduced by 20% from the conventional estimation. In addition, we find that the resistive flux consumption is closely related to the volume averaged electron temperature and not to the profile shape. Using this relation, the required heating power is estimated to be 31 MW based on a well established global confinement scaling, ITER L-89P. As a result, it is clarified that the CS flux consumption can be reduced by 20% even when a strongly reversed shear q profile is avoided using 20-31 MW of EC heating. This reduction of the flux consumption accounts for 10% reduction of the CS radius. It is also clarified that
the reduction of the CS flux consumption up to 25% is possible in general when the
temperature profile and the q profile is optimized.
書誌情報 Nuclear Fusion

巻 57, 号 1, p. 016015-1-016015-12, 発行日 2016-10
出版者
出版者 IOP Publishing
DOI
識別子タイプ DOI
関連識別子 10.1088/0029-5515/57/1/016015
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