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Non-disruptive error field measurement in DIII-D low safety factor plasmas and projection to ITER

Q.M. Hu, N.C. Logan, C. Paz-Soldan, J. Barr, S.K. Kim, J. Hanson, Y.Z. Jiang, S.M. Yang, A. Bortolon, W. Choi2025年1月Nuclear FusionIF 3出版社

Previous experiments in DIII-D (Paz-Soldan et al 2022 Nucl. Fusion62 126007) introduced a method to identify intrinsic error fields (EFs) in tokamaks with minimal disruption risk by promptly healing driven magnetic islands during the conventional 'compass scan'. This paper presents recent experimental and numerical advancements in extending this approach to low q95 plasmas, and projects its applicability to ITER. Non-disruptive EF measurement is achieved at q95 = 4.5 and 3.9 without any initial EF correction (EFC) by reducing the time between the occurrence of the locked mode (LM) and control action to 10 ms and increasing the density 50%–100%. However, 50% correction of the intrinsic EF is required to achieve island healing at q95 = 3.2 with 10 ms delay for the control action. Nonlinear two-fluid modeling with the TM1 code reproduces the DIII-D experimental observations, indicating that promptly turning off the 3D coil current reduces both magnetic island width and electromagnetic force, while raising the density increases plasma viscosity, facilitating magnetic island healing. The simulations show that for scenarios with q95 = 3.2, lowering the control action time to 5 ms will lead to island healing without EFC. TM1 simulations are extended to future ITER scenarios with 5 MA and 7.5 MA plasma currents, predicting the dependence of required density rise on action time and EF amplitude. These simulations indicate that, benefiting from the much longer resistive time, island healing can be successfully achieved in ITER when taking control action 100–500 ms after a LM occurrence.

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diii-d高精度(タイトル一致)iter高精度(タイトル一致)

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ITERDIII-DError fieldSafety factor

AIによる論文要約

DIII-Dの低安全係数プラズマにおける非破壊的な誤差磁場測定と ITER への外挿
JAこの論文は、トカマクの誤差磁場の同定と補正に関心のある核融合研究者や実験家に役立つでしょう。また、トカマクプラズマの安定性と制御に関心のある学生にも有益です。#トカマク #誤差磁場 #プラズマ安定性 #DIII-D #ITER
LLM向け: {'Title': 'DIII-Dの低安全係数プラズマにおける非破壊的な誤差磁場測定と ITER への外挿', 'Author(s)': '不明', 'Rese…

この論文は、DIII-Dトカマクにおける非破壊的な誤差磁場測定手法の最新の進展と、ITER への適用可能性を示しています。実験と数値シミュレーションにより、高密度化と迅速な制御動作により、低安全係数プラズマでも誤差磁場の同定と補正が可能であることが明らかになりました。これらの知見は、ITER などの将来の大型トカマクでの安定運転に貢献するでしょう。

Non-disruptive error field measurement in DIII-D low safety factor plasmas and projection to ITER
ENThis paper is relevant for fusion researchers working on error field correction and disruption mitigation in tokamaks, as it demonstrates a non-disruptive technique that can be applied to low safety factor plasmas and potentially to ITER.#FusionResearch #ErrorFieldCorrection #DisruptionMitigation #Tokamak
LLM向け: {'Title': 'Non-disruptive error field measurement in DIII-D low safety factor pl…

This paper presents a method to identify and correct intrinsic error fields in tokamaks without causing disruptions, even in low safety factor plasmas. The approach involves promptly healing magnetic islands by adjusting the 3D coil current and increasing plasma density. Simulations show this method can be applied to ITER, predicting the required density rise and control action time for successful island healing.

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