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SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas

N. Rivals, P. Tamain, Y. Marandet, X. Bonnin, J.-S. Park, H. Bufferand, R.A. Pitts, G. Falchetto, H. Yang, G. Ciraolo2025年2月Nuclear FusionIF 3出版社

The onset of detachment in the ITER machine is analyzed in this work through the help of 2D-axisymmetric boundary plasma simulations with the SOLEDGE3X-EIRENE code, which features a numerical domain for the plasma solver extending up to the first wall. The plasma boundary is computed in scenarios from the first non-active phase of ITER, in pure H and at 20 MW. This set of simulations is used in two aspects: first, to study the plasma detachment in the divertor, and second, the plasma conditions, fluxes, and beryllium erosion at the first wall. Here, the code results are also compared to those obtained with the well-established SOLPS-ITER code, which includes a plasma numerical domain only covering the main SOL. Results show an increase in the SOL width λq with increasing density, and a detailed analysis is carried out, for the first time, on each of the different plasma-neutral interactions in the code's physics model in EIRENE. The gross beryllium erosion rates of first wall panels are estimated from 2D simulations, with the aim of assessing their sensitivity to two parameters: the divertor density regime, and the presence of density shoulders in the far-SOL formed by enhanced perpendicular transport at this location. The erosion contributions from neutrals and ions are considered in each case, and the charge-exchange atoms fluxes and energy distributions are provided, highlighting the two atom populations (cold and charge-exchange).

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AIによる論文要約

ITE Rの非アクティブ相における全容器プラズマ境界シミュレーション
JAこのペーパーは、ITER機器の境界プラズマ物理を理解したい核融合研究者に有益です。プラズマ分離の発生メカニズムや、第一壁での材料浸食に関心がある研究者に特に役立つでしょう。#ITER #プラズマ境界 #ダイバータ #ベリリウム浸食 #SOLEDGE3X
LLM向け: {'Title': 'ITE Rの非アクティブ相における全容器プラズマ境界シミュレーション', 'Author(s)': '不明', 'Research Obj…

この研究では、SOLEDGE3X-EIRENEコードを使用して、ITER機器の第1非アクティブ相のシナリオにおけるプラズマ分離の発生を分析しています。シミュレーションは、ダイバータでのプラズマ分離と第一壁でのベリリウム浸食の両方を対象としています。結果は、SOL幅の増加や、中性粒子と荷電粒子の相互作用の詳細な分析など、重要な知見を示しています。

SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas
ENThis paper should be read by fusion researchers, plasma physicists, and engineers involved in the design and operation of ITER, as it offers a comprehensive understanding of the complex plasma boundary behavior and its implications for the first wall.#ITERplasmasimulations #plasmaboundary #detachment #firstwallerosion
LLM向け: {'Title': 'SOLEDGE3X full vessel plasma boundary simulations of ITER non-active …

This paper presents a detailed analysis of plasma detachment and first wall erosion in the ITER tokamak using advanced 2D boundary plasma simulations. The study examines the impact of increasing plasma density on the scrape-off layer width and various plasma-neutral interactions, providing valuable insights for ITER operations.

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