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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/47757f4481337-665f-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× 鈴木, 隆博× 林, 伸彦× 白石, 淳也× 坂本, 宜照× 井手, 俊介× 久保, 博孝× 鎌田, 裕× 若月 琢馬× 鈴木 隆博× 林 伸彦× 白石 淳也× 坂本 宜照× 井手 俊介× 久保 博孝× 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. |
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| 書誌情報 |
Nuclear Fusion 巻 57, 号 1, p. 016015-1-016015-12, 発行日 2016-10 |
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| 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 | |||||
