J-TEXT托卡马克铁芯对三维磁场的影响

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Hao Man, Nengchao Wang, Zhengkang Ren, Yangbo Li, Feiyue Mao, Xinchen Yao, Chuanxu Zhao, Chengshuo Shen, Song Zhou, Yonghua Ding, the J-TEXT Team
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引用次数: 0

摘要

非轴对称安装在托卡马克中的铁磁材料会对轴对称磁场产生三维误差,即误差场(EF)。在J-TEXT托卡马克上,实验测量了双肢铁芯诱导的EF,定义了其环面模数n = 2。通过加入三维铁芯模型,有限元分析(FEA)再现了实验测量结果,进一步揭示了该电磁场的特性,并评估了其对等离子体实验的潜在影响。双肢铁芯对n = 2螺旋线圈(称为外旋转变换线圈)磁场的影响(李彦斌等,2024 Fusion Eng.)。Des. 206 114,591),并对铁芯的饱和效应进行了定性讨论。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Influence of the iron core on three-dimensional magnetic field in the J-TEXT tokamak
The ferromagnetic materials non-axisymmetrically installed in tokamaks can induce three-dimensional (3D) errors to the axisymmetric magnetic field, i.e., the error field (EF). On the J-TEXT tokamak, the two-limb iron core induced EF is measured in the experiments, which defined its toroidal mode number n = 2. By including the 3D iron core model, the finite element analysis (FEA) reproduces the experimental measurement, further reveals characteristics of this EF and evaluates its potential impact on plasma experiments. The influence of the two-limb iron core on the magnetic field from the n = 2 helical coils, called external rotational transform coils (Li Y B et al. 2024 Fusion Eng. Des. 206 114,591), is also studied, along with a qualitative discussion on the saturation effect of iron core.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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