Temperature field calculation and cooling water design of the pyrobreaker in Quench protect system

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

Fusion Engineering and Design Pub Date : 2025-04-22 DOI:10.1016/j.fusengdes.2025.115109

Zhenhan Li , Hua Li , Jifei Ye , Qianglin Xu , Xiaohua Bao , Ge Gao

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引用次数: 0

Abstract

The pyrobreaker, which serves as a backup protection switch in the Quench Protection System (QPS), is critical to maintaining the safe operation of superconducting fusion devices. However, the thermal energy generated by sustained current flow rises dramatically with current levels, which could harm the pyrobreaker and increasing the risk of QPS failure. Therefore, a reliable cooling water system is essential for ensuring the long-term reliability and stability of both the pyrobreaker and the overall system. First, the paper presents the overall structure and operational principles of the pyrobreaker in the QPS and then provides a detailed description of the cooling water system design. Second, the temperature of the cooling water system is calculated and analyzed theoretically by a numerical simulation model. Three, a 100kA test system platform was built to verify the feasibility and effectiveness of the cooling water system design. The results show that the cooling system effectively meets the temperature control requirements under 100 kA working conditions. This paper provides considerable theoretical support and a practical reference for ensuring QPS reliability and long-term stability in superconducting fusion systems.

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失火保护系统中高温断路器的温度场计算及冷却水设计

高温断路器作为超冷保护系统（QPS）中的备用保护开关，对维持超导聚变装置的安全运行至关重要。然而，持续电流产生的热能随着电流水平的增加而急剧上升，这可能会损害烧碎器并增加QPS失效的风险。因此，一个可靠的冷却水系统对于保证烧断机和整个系统的长期可靠性和稳定性至关重要。本文首先介绍了QPS中灭焰器的总体结构和工作原理，然后详细介绍了冷却水系统的设计。其次，通过数值模拟模型对冷却水系统温度进行了理论计算和分析。三是搭建了100kA测试系统平台，验证了冷却水系统设计的可行性和有效性。结果表明，该冷却系统能有效满足100 kA工况下的温控要求。本文为保证超导聚变系统QPS的可靠性和长期稳定性提供了重要的理论支持和实践参考。

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.