Preliminary study on electrical wire explosion utilized in pyro-breaker

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-11-13 DOI:10.1016/j.fusengdes.2024.114726

Zhenhan Li , Hua Li , Cunwen Tang , Guanghong Wang , Xiaohua Bao , Ge Gao

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Abstract

Quench protection system (QPS) is critical for ensuring the safety operation of superconducting magnets in nuclear fusion devices, while the pyro-breaker is wildly used in QPS for backup protection. This paper discusses the feasibility of using Underwater Electrical Wire Explosion (UEWE) to drive pyro-breaker. Firstly, the overall structure and the driving mechanism of arc contact of pyro-breaker are analyzed. Secondly, the detonation pressure required for contact breaking is measured by experiment. Then a microsecond-level UEWE experimental platform was established to test the discharge characteristics and shock wave intensity during the electrical explosion process. Finally, the detonation pressure generated by UEWE is measured and compared with contact driving mechanism of pyro-breaker. The experiment demonstrates that the UEWE has sufficient potential for replacing the explosive and driving the pyro-breaker. This study provides a new pathway for the design of the pyro-breaker.

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关于火工破碎机中使用的电线爆炸的初步研究

淬火保护系统（QPS）是确保核聚变装置中超导磁体安全运行的关键，而在 QPS 中，火破器被广泛用于后备保护。本文讨论了利用水下电线爆炸（UEWE）驱动火破的可行性。首先，分析了泄爆器的整体结构和电弧接触驱动机理。其次，通过实验测量了触点断裂所需的爆破压力。然后，建立了微秒级 UEWE 实验平台，测试电爆过程中的放电特性和冲击波强度。最后，测量了 UEWE 产生的爆炸压力，并将其与火工破碎机的接触驱动机理进行了比较。实验结果表明，超高压电子元件具有足够的潜力来替代炸药并驱动火破。这项研究为火工爆破装置的设计提供了一条新的途径。

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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.