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Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC

E. Tholerus, L. Garzotti, V. Parail, Y. Baranov, X. Bonnin, G. Corrigan, F. Eriksson, D. Farina, L. Figini, D.M. Harting2025年3月Nuclear FusionIF 3出版社

In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively in these stages to ensure negligible production of neutrons from fusion reactions. With the expected higher L–H power threshold of hydrogen and helium plasmas compared to corresponding D and D/T plasmas, it is uncertain whether available auxiliary power systems are sufficient to operate in stable type-I ELMy H-mode. This has been investigated using integrated core and edge/SOL/divertor modelling with JINTRAC. Assuming that the L–H power threshold is well captured by the Martin08 scaling law, the presented simulations have found that 30 MW of ECRH power is likely required for the investigated hydrogen plasma scenarios, rather than the originally planned 20 MW in the 2016 Staged Approach ITER Baseline. However, past experiments have shown that a small helium fraction (∼10%) can considerably reduce the hydrogen plasma L–H power threshold. Assuming that these results extrapolate to ITER operation regimes, the 7.5 MA/2.65 T hydrogen plasma scenario is likely to access stable type-I ELMy H-mode operation also at 20 MW of ECRH.

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iter高精度(タイトル一致)

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ITEREdge localized modeH-modeELMy H-mode

AIによる論文要約

ITER 前融合動力運転のための ELMy H モード運転のアクセスと持続性
JAこの論文は、ITER の初期運転段階における ELM 制御に関心のある研究者や技術者に有用です。特に、プラズマ加熱パワーの確保や ELM 制御手法の検討に役立つと考えられます。#ITER #ELM_mitigation #H-mode #L-H_transition #ECRH
LLM向け: {'Title': 'アクセスと持続性のELMy H モード運転 - ITER 前融合運転のために', 'Author(s)': '不明', 'Research…

この論文は、ITER の初期運転段階でELM緩和システムを導入するために、水素またはヘリウムプラズマを用いたタイプI ELMy H モード運転の可能性を検討したものです。シミュレーションの結果、水素プラズマの場合は 30 MW の ECRH 電力が必要と予想されますが、ヘリウム混入により L-H 遷移閾値が低下すれば、20 MW の ECRH で安定したタイプI ELMy H モード運転が可能と示唆されています。

[Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC]
ENThis paper should be read by fusion researchers and ITER project team members who are interested in understanding the operational challenges and potential solutions for the initial stages of ITER operation.#ITER #ELMy_H-mode #JINTRAC #Plasma_Modeling #Fusion_Power_Operation
LLM向け: {'Title': 'Access and sustainment of ELMy H-mode operation for ITER pre-fusion p…

This paper investigates the feasibility of achieving stable ELMy H-mode operation in ITER's initial hydrogen/helium plasma stages using integrated core and edge/SOL/divertor modeling. It suggests that 30 MW of ECRH power may be required, rather than the planned 20 MW, to access this regime, but a small helium fraction could reduce the power threshold.

[ITER 前期運転のためのELMy H モード運転の確保と維持]
JAこの論文は、ITER の初期運転計画に関心のある研究者や技術者に役立つと考えられます。プラズマ物理や核融合炉設計に携わる学生にも、ITER の運転課題を理解する上で参考になると思われます。#ITER #ELM #H-mode #プラズマ物理 #核融合炉設計
LLM向け: {'Title': 'ITER 前期運転のためのELMy H モード運転の確保と維持', 'Author(s)': '不明', 'Research Object…

この論文は、ITER の初期運転段階でELM緩和システムを導入するために、水素またはヘリウム プラズマを用いた安定なタイプI ELMy H モード運転の可能性を検討したものです。統合コアエッジ/SOL/ダイバータモデリングにより、水素プラズマの L-H 遷移閾値が高いことから、20 MW の加熱では不十分で 30 MW が必要と示唆されています。ただし、少量のヘリウム混入で閾値が低下する可能性も指摘されています。

[Access and sustainment of ELMy H-mode operation for ITER pre-fusion power operation plasmas using JINTRAC]
ENThis paper is relevant for fusion researchers and ITER operation planners, as it provides insights into the power requirements and plasma conditions needed to achieve stable ELMy H-mode operation during ITER's early non-fusion power phase.#ITER #ELMy_H-mode #Integrated_Modeling #Plasma_Scenarios #Auxiliary_Power_Requirements
LLM向け: {'Title': 'Access and sustainment of ELMy H-mode operation for ITER pre-fusion p…

This paper investigates the feasibility of operating ITER in a stable ELMy H-mode regime during its initial non-fusion power stage, using integrated core and edge/SOL/divertor modeling. It suggests that 30 MW of ECRH power may be required, rather than the originally planned 20 MW, to access this regime in hydrogen plasmas. However, a small helium fraction could reduce the power threshold, potentially allowing 20 MW to be sufficient.

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