用于 J-TEXT 上等离子体干扰缓解的 EMPI 系统优化设计与实验测试

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

Fusion Engineering and Design Pub Date : 2024-10-26 DOI:10.1016/j.fusengdes.2024.114701

Y.L. Yu , Z.Y. Chen , W. Yan , S.G. Xia , N.C. Wang , Z.S. Nie , X. Zhou , Y. Sheng , Y.W. Sun , J.G. Fang , Y. Zhong , the J-TEXT Team

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引用次数: 0

摘要

等离子体破坏会对托卡马克造成重大损害。目前，缓解中断的主要方法是注入大量杂质。电磁注入法具有高注入速度和快速反应时间，是一种很有前途的杂质注入技术。由 J-TEXT 团队开发的第一个电磁颗粒注射系统（EMPI）能够以高速发射颗粒，并配有专门的减速轨道，确保电枢和颗粒的安全分离。然而，该系统缺乏电枢回收装置和真空系统。在这项工作中，开发了第二代 EMPI，它具有真空系统和弯曲的回收轨道。弧形回收轨道有利于电枢的顺利回收，提高了回收过程的安全性。此外，新系统还采用了增强型轨道设计，提高了发射性能。测试结果表明，新型 EMPI 的最大电流降低了约 60%，而最大发射速度提高了约 20%。

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Optimal design and experimental testing of EMPI system for plasma disruption mitigation on J-TEXT

Plasma disruptions can cause significant damage to tokamak. Currently, the primary method for mitigating disruptions is the injection of a substantial amount of impurities. The electromagnetic injection method offers a high injection speed and rapid response time, making it a promising technique for impurity injection. The first Electromagnetic Pellet Injection System (EMPI), developed by the J-TEXT team, is capable of launching pellets at high velocities and features a specialized deceleration rail that ensures safe separation of the armature and pellet. However, this system lacks an armature recovery device and a vacuum system. In this work, a second generation EMPI has been developed, which has a vacuum system and a curved recovery rail. The curved recovery rail facilitates the smooth retrieval of the armature, enhancing the safety of the recycling process. Additionally, this new system employs an augmented rail design that improves launch performance. Test results indicate that the maximum current of the new EMPI has been reduced by approximately 60%, while the maximum launch speed has increased by around 20%.

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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.