Model experiments to the conductivity of turn insulation of large fusion magnets during unmitigated quench

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Linlin Fang , Yury Ilin , Xiongyi Huang , Qingxiang Ran , Zhiheng Dai , Cao Wang , Guoliang Li , Jinxing Zheng , Kun Lu , Yuntao Song
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引用次数: 0

Abstract

The ITER superconducting magnet system stores a significant amount of energy. During an unmitigated quench, the undissipated energy can cause localized conductors to melt and break, leading to the formation of arcs. These arcs not only directly damage the conductor but may also cause indirect damage to adjacent components, such as the vacuum vessel and cryostat, potentially leading to the release of radioactivity. As the arcs form and develop in the magnet, the turn insulation gradually carbonizes. If the resistivity of the carbonized insulation is sufficiently low, it can affect the current distribution and arc propagation. To understand the conductivity of the turn insulation in a superconducting magnet during an unmitigated quench, this paper references the ITER magnet design and manufactures simplified samples. The experimental setup was established, and the samples were heated under a direct current. The voltage and temperature signals of the samples were analyzed during testing to gain a preliminary understanding of the turn insulation's conductivity from room temperature to 1000 °C over a heating period of several hundred seconds.
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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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