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A simple model to evaluate the heat flux onto the EU-DEMO plasma facing components during the current quench

G. Pautasso, M. Siccinio, F. Maviglia, E. Fable, T. Pütterich2025年6月Nuclear FusionIF 3出版社

A model for the plasma evolution during the current quench is presented in this paper: it allows to simulate the evolution of the phenomenon, carry on parametric studies and calculate the heat loads on the tokamak first wall. During the disruption of a tokamak plasma, the current decay rate, the dissipation of the magnetic energy, the repartition of the dissipated energy in different channels, the magnitude of the halo current and the width of the halo region are all functions of the plasma temperature and of the impurity densities. The energy balance equation determines the whole disruption evolution and it must be solved during the current quench, in the close flux surface region and in the halo.

日本語訳

本論文では、電流クエンチ中のプラズマの時間発展のためのモデルを提示する。このモデルにより、現象の時間発展をシミュレートし、パラメトリック研究を実施し、トカマク第一壁への熱負荷を計算することができる。トカマクプラズマのディスラプション中に、電流減衰率、磁気エネルギーの散逸、散逸エネルギーの異なるチャネルへの配分、ハロー電流の大きさ、およびハロー領域の幅は、すべてプラズマ温度と不純物密度の関数である。エネルギー平衡方程式はディスラプション全体の時間発展を決定し、それは電流クエンチ中に、閉磁束面領域とハロー領域において解かれなければならない。

wiki

DEMOPlasma-facing componentEU-DEMO

AIによる論文要約

プラズマ対向部材への熱流束を評価する簡単なモデル
JAプラズマ物理、核融合炉設計の研究者や学生が対象で、トカマクプラズマの電流消失時の挙動と第一壁への熱負荷を理解するのに役立つ。#プラズマ物理 #核融合炉設計 #トカマク #電流消失 #熱負荷
LLM向け: {'Title': 'プラズマ対向部材への熱流束を評価する簡単なモデル', 'Author(s)': '不明', 'Research Objective': '…

この論文では、トカマクプラズマの電流消失期における現象の進化をシミュレーションし、第一壁への熱負荷を計算するモデルを提示しています。プラズマ温度や不純物密度に依存する電流減衰率、磁気エネルギー散逸、散逸エネルギーの配分、ハロー電流の大きさとその幅などを解析することで、電流消失期全体の過程を記述できます。

A simple model to evaluate the heat flux onto the EU-DEMO plasma facing components during the current quench
ENThis paper should be read by fusion researchers and engineers working on disruption mitigation and plasma-wall interactions in tokamak devices.#TokamakDisruptions #PlasmaFacingComponents #HeatFlux
LLM向け: {'Title': 'A simple model to evaluate the heat flux onto the EU-DEMO plasma faci…

This paper presents a model to simulate the evolution of plasma disruptions in tokamaks, which is crucial for evaluating the heat loads on the first wall. The model considers the current decay, magnetic energy dissipation, and impurity effects during the current quench phase.

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