Discussion on reliability and test number of switches in Tokamak fast discharge units

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-07-18 DOI:10.1016/j.fusengdes.2024.114599
Meng Xu , Hua Li , Zhiquan Song , Guanghong Wang , Jianjun Chen , Zhenhan Li , Peng Fu
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Abstract

High-power switches, as the important active part of Fast Discharge Unit (FDU) in Tokamak, are designed to interrupt the circuit current and transfer the quench energy for protecting expensive superconducting magnets. Hence, their reliability has always been highly underlined. In this paper, the reliability and test number of FDU switches are discussed, mainly including three issues. First, the FDU configuration characteristics of different types of superconducting magnets are introduced, and explanations and calculations on reliability are provided. Second, the reliability interval estimation after a certain test number is discussed by using the binomial distribution theory. Three, the compliance test based on the claimed reliability is studied, and two types of test plans are discussed and compared to derive the test number. The discussion in this paper focuses on the FDU switches and provides valuable guidance for their reliability test and assessment.

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关于托卡马克快速放电装置开关的可靠性和测试次数的讨论
大功率开关是托卡马克中快速放电装置(FDU)的重要有源部分,用于中断电路电流和传输淬火能量,以保护昂贵的超导磁体。因此,其可靠性一直备受关注。本文讨论了 FDU 开关的可靠性和测试次数,主要包括三个问题。首先,介绍了不同类型超导磁体的 FDU 配置特征,并对可靠性进行了解释和计算。其次,利用二项分布理论讨论了一定测试次数后的可靠性区间估计。第三,研究了基于声称可靠性的符合性测试,并讨论和比较了两种类型的测试计划以得出测试次数。本文重点讨论了 FDU 交换机,为其可靠性测试和评估提供了有价值的指导。
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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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