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First EMC3-EIRENE modeling of JT-60SA edge plasmas with/without RMP field
https://repo.qst.go.jp/records/79524
https://repo.qst.go.jp/records/79524e7786bf3-cb94-483b-83e2-df36ecd4b423
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2020-03-17 | |||||
| タイトル | ||||||
| タイトル | First EMC3-EIRENE modeling of JT-60SA edge plasmas with/without RMP field | |||||
| 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 |
Tanaka, H.
× Tanaka, H.× Kawamura, G.× K. Hoshino× Kobayash, M.× Matsunaga, Go× Suzuki, Y.× Lunt, T.× Y. Feng× N. Ohno× Matsunaga, Go |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | For the ITER and DEMO reactors, transient heat load induced by large edge localized mode (ELM) must be mitigated or suppressed to maintain the surface condition of the divertor plate. From recent studies in tokamak devices, an application of the resonant magnetic perturbation (RMP) field is thought to be one of the effective solutions. The RMP has an inherently three-dimensional (3D) nature, causing a non-axisymmetric modification of the divertor heat flux profile. Due to the RMP, splitting of a strike point is observed. Recent experiment in ASDEX-U indicated that the RMP induces the modification of toroidal and radial distributions of the heat flux, although the toroidally averaged radial heat flux is the same with that without the RMP case. In addition, the degree of the heat flux variation was found to depend on the upstream plasma condition. The research of the RMP effect for the divertor heat load is being conducted in both experiments and numerical simulations. The ELM mitigation experiment with RMP in JT-60SA tokamak, which is being constructed, is scheduled as a key research item. Before the experiment, it is important to predict the divertor footprint pattern and its characteristics by using a modeling code. For this aim, the 3D plasma fluid transport and kinetic neutral transport code, “EMC3-EIRENE”, is suitable, and it has been applied to several devices. Therefore, we have started the EMC3-EIRENE modeling of JT-60SA edge plasmas with/without the RMP field. At first, we calculated pure deuterium plasma in an axisymmetric magnetic configuration grid, and then results were compared with those from the two-dimensional (2D) transport code “SONIC”. As a result, similar amplitude and decay of the heat flux profile on the divertor plate were obtained. After that, the grid equipping the RMP field with the toroidal mode number of n = 3 was generated (so-called an ITER-like scenario). From a 120-degree range calculation in the toroidal direction, lobe structures and a footprint splitting were first confirmed in the EMC3-EIRENE calculation of JT-60SA, being consistent with the previous magnetic field tracing. We will present the above-mentioned results and discuss RMP effects on footprint profile, flow, recycling, and so on. | |||||
| 書誌情報 |
Contributions to Plasma Physics 巻 60, 号 5-6, 発行日 2020-03 |
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| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 1521-3986 | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1002/ctpp.201900114 | |||||
| 関連サイト | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | https://doi.org/10.1002/ctpp.201900114 | |||||
