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Simulation study of the influence of drifts on the upstream and target heat flux width under different BT directions

Jin Guo, Shifeng Mao, Lingyi Meng, Guoliang Xu, Rui Ding, Minyou Ye2024年10月Nuclear FusionIF 3出版社

The heat flux width (λq) is a key parameter determining the heat load at divertor targets. In recent years, drifts have been found to play a remarkable role in the edge plasma transport, while its influence on λq has not been well understood. Investigations of the influence of drifts on λq, systematic simulations using the SOLPS-ITER code are performed in this work. The statistics of the simulation results show that the drift under favorable/unfavorable BT tends to increase the λq in the outer/inner side and decrease the λq in the other side, which is consistent with the experiment observations. At the upstream and the target, the mechanisms of the influence of the drifts on λq are different. The upstream λq (λq,u) is directly affected by the drift-induced convective heat flux, while λq at the target (λq,t) is indirectly influenced through heat conduction (in the high-recycling regime) and the sheath (in the detached regime) due to the change of plasma parameters there. Furthermore, the synergetic effect of geometry and drift under favorable BT leads to an anomalously large λq,t in the inner side at high density.

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AIによる論文要約

ドリフトが上流および標的熱流束幅に及ぼす影響のシミュレーション研究
JA本論文は、核融合プラズマの熱負荷評価に関心のある研究者や学生向けです。プラズマ輸送現象とその影響について理解を深めることができます。#核融合 #プラズマ #熱負荷 #ドリフト #SOLPS-ITER
LLM向け: {'Title': 'ドリフトが上流および標的熱流束幅に及ぼす影響のシミュレーション研究', 'Author(s)': '不明', 'Research Obje…

本研究では、ドリフトが熱流束幅(λq)に及ぼす影響をSOLPS-ITERコードを用いて系統的にシミュレーションしています。その結果、ドリフトにより上流のλq,uと標的のλq,tに異なる影響が見られることが分かりました。上流のλq,uはドリフトによる対流熱流束の変化により直接影響を受けますが、標的のλq,tは高リサイクリング領域では熱伝導、分離領域では磁力線に沿った熱流束の変化を通して間接的に影響を受けます。また、有利なBT方向でのジオメトリとドリフトの相乗効果により、標的の内側でλq,tが異常に大きくなることが示されています。

Simulation study of the influence of drifts on the upstream and target heat flux width under different BT directions
ENThis paper would be of interest to fusion researchers and engineers working on plasma edge physics, divertor design, and heat load management in fusion reactors.#FusionReactor #PlasmaEdgePhysics #DivertorDesign #HeatLoadManagement
LLM向け: {'Title': 'Simulation study of the influence of drifts on the upstream and targe…

This paper investigates how plasma drifts affect the width of heat flux at the divertor target in fusion reactors. It shows that drifts can increase the heat flux width on one side and decrease it on the other, depending on the direction of the magnetic field. This is important for understanding and managing the heat load on fusion reactor components.

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