HL-3托卡马克垂直失稳主动控制电源

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Zheng Xue, Xiong Zhenming, Liu Panle, Wang Yingqiao, Xuan Weimin, Li bo, Chen Yihang
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引用次数: 0

摘要

为了减轻等离子体垂直不稳定性,确保高质量的物理实验和机器的安全,垂直不稳定性主动控制电源(VS PS)必须对真空容器内的偏置等离子体垂直位移事件做出快速响应。本文介绍了基于IGBT技术的级联h桥结构的设计,标志着在HL-3托卡马克上首次实现了VS PS。与电网提供的传统电源不同,VS PS由300 MVA双Y六相电机发电机供电,这需要仔细考虑其独特的供电条件。h桥的模块化设计允许可扩展性,以满足未来对更高操作参数的需求。级联的h桥结构提高了输出电压,降低了输出端的总谐波失真(THD)。该系统有效地满足了HL-3托卡马克中等离子体垂直不稳定性的控制要求,控制响应时间约为200 μs,控制了1.6伸长率和500 kA等离子体电流下的等离子体条件。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Vertical instability active controlled power supply of HL-3 tokamak
To mitigate plasma vertical instability and ensure high-quality physical experiments as well as the safety of the machine, the vertical instability active controlled power supply (VS PS) must respond rapidly to bias plasma vertical displacement events within the vacuum vessel. This paper presents the design of a cascaded H-bridge structure based on IGBT technology, marking the first implementation of a VS PS in the HL-3 tokamak. Unlike traditional power sources supplied by the grid, the VS PS is powered by a 300 MVA double Y six-phase motor-generator, which necessitates careful consideration of its unique supplying conditions. The modular design of the H-bridge allows for scalability to meet future demands for higher operational parameters. The cascaded H-bridge configuration enhances output voltage and reduces total harmonic distortion (THD) at the output side. The system effectively meets the control requirements for plasma vertical instability in the HL-3 tokamak, achieving a control response time of approximately 200 μs and managing plasma conditions under 1.6 elongation and 500 kA plasma current.
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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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