Final development and preliminary experiment progress of in-vessel resonant magnetic perturbation coils system on HL-3 tokamak

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2024-10-29 DOI:10.1016/j.fusengdes.2024.114702

A. Wang , T.F. Sun , W. Chen , B.T. Cui , J.M. Gao , S.Y. Liang , M.Y. He , X.Q. Ji

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Abstract

This paper details the design, construction, and analysis of resonant magnetic perturbation (RMP) with 16 in-vessel coils on the HL-3 to investigate the interactions between resonant magnetic perturbations and magnetohydrodynamic instabilities. The toroidal × poloidal = 8 × 2 arrangement allows for a more flexible magnetic field and spectrum shape. The RMP coil was designed as a four-turn double-layer winding. The coils are adopted with a water-cooled hollow copper conductor insulated with a MgO layer and then housed inside a welded stainless steel shell. The thermal and electromagnetic loads of the coil were evaluated by simulation, which meets the requirements. Four power supplies are integrated into the HL-3 system that can provide DC and AC with various waveforms. The maximum DC amplitude is 3 kA, while the AC frequency can reach up to 1 kHz. In the HL-3 H-mode plasmas, an experimental result of edge localized mode (ELM) mitigation with n = 1 RMPs which are oddly paired by 8 RMP coils is also given for the first time in this paper.

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HL-3 托卡马克舱内共振磁扰动线圈系统的最终开发和初步实验进展

本文详细介绍了在 HL-3 上设计、建造和分析带有 16 个舱内线圈的共振磁扰动（RMP），以研究共振磁扰动与磁流体力学不稳定性之间的相互作用。环形 × 极环形 = 8 × 2 的排列方式使磁场和频谱形状更加灵活。RMP 线圈设计为四匝双层绕组。线圈采用水冷空心铜导体，绝缘层为氧化镁，然后装在焊接的不锈钢外壳内。通过仿真评估了线圈的热负荷和电磁负荷，结果符合要求。HL-3 系统集成了四个电源，可提供各种波形的直流和交流电。最大直流电幅为 3 kA，交流电频率可达 1 kHz。在 HL-3 H 模式等离子体中，本文还首次给出了 n = 1 个 RMP（由 8 个 RMP 线圈奇数配对）的边缘局部模式（ELM）缓解实验结果。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

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.