Application of the passive plates for magnetic compression device based on field-reversed configuration

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
ZhuoLong Li, ZhiPeng Chen, YuJun Zhang, MingBo Zong, Rui Liu, Bo Rao, Yong Yang
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引用次数: 0

Abstract

The magnetic compression device based on field-reversed configuration (FRC) aims to obtain high-quality FRC through collision-merging and magnetic compression. To mitigate the expansion of FRCs during collision and reduce axial ripple in the compression magnetic field, a solution of installing passive plates between the compression coils array and the confinement chamber is proposed. The simulation study by COMSOL Multiphysics mainly focuses on two aspects: suppressing plasma expansion and optimizing axial field uniformity. The passive plates are divided poloidally into four segments to ensure that the field penetration will not be impeded. The results demonstrate that the eddy currents in the passive plates suppress radial plasma expansion by enhancing its external magnetic field by up to 30 %. The currents also lead to a reduction in axial ripple of compression field in regions covered by the plates. The accompanying poloidal ripple is suppressed via narrowing plate gaps and implementing non-contact overlapping arrangements, with its magnitude optimized to below 5.6 %. Finally, the mechanism by which the passive plates modulate magnetic field is elucidated by illustrating the distribution of eddy currents within the plates.
基于反场结构的无源极板在磁压缩装置中的应用
基于磁场反向结构的磁压缩装置旨在通过碰撞合并和磁压缩获得高质量的磁场反向结构。为了减轻碰撞过程中FRCs的膨胀,减小压缩磁场的轴向脉动,提出了在压缩线圈阵列与约束室之间安装无源板的解决方案。COMSOL Multiphysics的模拟研究主要集中在抑制等离子体膨胀和优化轴向场均匀性两个方面。无源板被分成四段,以确保磁场穿透不会受到阻碍。结果表明,无源板中的涡流通过增强其外部磁场来抑制径向等离子体膨胀达30%。该电流还导致被板覆盖区域的压缩场轴向纹波减小。通过缩小极板间隙和实施非接触重叠安排,抑制了伴随的极向纹波,其幅度优化到5.6%以下。最后,通过分析无源板内涡流的分布,阐明了无源板调制磁场的机理。
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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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