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Impurity leakage mechanisms in the Wendelstein 7-X island divertor under friction-dominated conditions

V.R. Winters, F. Reimold, Y. Feng, V. Perseo, M. Beurskens, S. Bozhenkov, K.J. Brunner, G. Fuchert, R. Koenig, J. Knauer2024年5月Nuclear FusionIF 3出版社

The EMC3-Eirene code was used to study the main impurity leakage mechanism for the island divertor in the standard magnetic field configuration. It was found that under experimentally accessible plasma scenarios in the last experimental campaign, the majority of the island scrape-off layer was friction-force dominated. The impurity force balance was only thermal force dominated for upstream locations closed to the last closed flux surface, beyond the island X-point. No impurity neutral ionization was found in this location and hence the parallel impurity transport provides excellent impurity retention. It was found that impurities approach the confinement region nonetheless via perpendicular transport across the island O-point near the parallel flow stagnation region. This finding points out the specific role of the parallel flow stagnation region in providing lower parallel convective transport and long impurity residence times, which makes non-parallel transport channels more important or even the dominant driver of impurity leakage. In line with the relevance of the particle build-up in the flow stagnation region, different retention behavior as a function of density is seen for various species, which is shown to be due to ionization length changes as the plasma background density is increased.

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wendelstein-7x高精度(タイトル一致)

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DivertorImpurityWendelsteinIsland divertor

AIによる論文要約

W7-Xアイランドダイバータにおける不純物漏洩メカニズム
JAこのペーパーは、プラズマ物理や核融合分野の研究者や学生に有益です。プラズマ閉じ込めにおける不純物挙動の理解を深めることができます。#W7-X #ImpurityTransport #PlasmaConfinement #FusionResearch

この論文は、W7-Xアイランドダイバータにおける主要な不純物漏洩メカニズムについて研究したものです。EMC3-Eireneコードを用いた解析の結果、実験的に到達可能な条件下では、アイランドスクレイプオフ層の大部分が摩擦力支配的であることが分かりました。不純物の並行輸送が優れた不純物保持をもたらしますが、O点近傍の並行流停滞領域を通じた垂直輸送が不純物漏洩の主要因となることが示されています。

Impurity leakage mechanisms in the Wendelstein 7-X island divertor under friction-dominated conditions
ENThis paper is of interest to fusion researchers and engineers working on divertor design and impurity control in stellarator-type fusion devices like Wendelstein 7-X.#FusionImpurityControl #StellatorDivertorDesign #ParallelFlowStagnation

This paper investigates the main impurity leakage mechanisms in the Wendelstein 7-X fusion reactor's island divertor under friction-dominated plasma conditions. The study finds that impurities can approach the confinement region via perpendicular transport across the island O-point near the parallel flow stagnation region, highlighting the importance of this region in impurity retention.

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