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JT-60SA edge plasma modeling under several resonant magnetic perturbation conditions

https://repo.qst.go.jp/records/85074
https://repo.qst.go.jp/records/85074
885e28aa-c2b8-4c08-88ba-3e0adf3960b0
Item type 会議発表用資料 / Presentation(1)
公開日 2022-03-02
タイトル
タイトル JT-60SA edge plasma modeling under several resonant magnetic perturbation conditions
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 Enomoto, S.

× Enomoto, S.

WEKO 1025863

Enomoto, S.

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Tanaka, H.

× Tanaka, H.

WEKO 1025864

Tanaka, H.

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Kawamura, G.

× Kawamura, G.

WEKO 1025865

Kawamura, G.

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Go, Matsunaga

× Go, Matsunaga

WEKO 1025866

Go, Matsunaga

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M. Kobayashi

× M. Kobayashi

WEKO 1025867

M. Kobayashi

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Hoshino, K.

× Hoshino, K.

WEKO 1025868

Hoshino, K.

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Y. Suzuki

× Y. Suzuki

WEKO 1025869

Y. Suzuki

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Kajita, S.

× Kajita, S.

WEKO 1025870

Kajita, S.

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Ohno, N.

× Ohno, N.

WEKO 1025871

Ohno, N.

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Go, Matsunaga

× Go, Matsunaga

WEKO 1025872

en Go, Matsunaga

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抄録
内容記述タイプ Abstract
内容記述 In fusion reactor, large transient heat load attributed to the edge localized mode (ELM) could damage the diverter plate. Therefore, it is needed to mitigate or supress the ELM amplitude and an application of the resonant magnetic perturbation (RMP) field is thought to be one of effective solutions. Because the RMP field has three-dimensional (3D) geometry, 3D plasma fluid transport and kinetic neutral transport code, ''EMC3-EIRENE'' is suitable to model the RMP effect on steady-state parameters. In previous researches, EMC3-EIRENE simulations of RMP effects are conducted in several devices such as NSTX, AUG, and ITER.
The construction of JT-60SA was completed in 2020, and various experiments will be conducted with RMP. Recently, although an EMC3-EIRENE modeling was firstly performed in JT-60SA, the applied RMP condition was only one case. Therefore, this study perform numerical simulations with several RMP strengthes in JT-60SA.
The divertor heat flux profiles with RMP coil currents of Ic = 0 (without RMP), 10, 20, and 30 kA are simulated. Here, plasma responce is not considered. Except for Ic = 0 case, the strike-point splitting patterns are found with the toroidal mode number of n = 3, which is the same of that of the RMP. Furthermore, by increasing the RMP coil current, enhancement of the splitting is found. We will present detailed relationships between the RMP strength and edge and divertor plasma parameters.
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 The 30th International Toki Conference on Plasma and Fusion Research
発表年月日
日付 2021-11-16
日付タイプ Issued
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