JT-60SA综合调试线圈通电试验

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

Fusion Engineering and Design Pub Date : 2025-04-19 DOI:10.1016/j.fusengdes.2025.115091

Kunihito Yamauchi , Shoichi Hatakeyama , Jun Okano , Yoshikazu Ohmori , Tsunehisa Terakado , Katsuhiro Shimada , Giampaolo Frello , Luca Novello

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引用次数: 0

摘要

2023年，在综合调试中，JT-60SA的所有线圈电源（PS）部件都使用相应的超导线圈进行了测试。最初，进行了单个线圈通电测试，以确认每个线圈PS组件的性能。随后，逐步进行综合线圈通电试验，逐步增加同时运行的超导线圈数量。结果证实，在2023年operation -1相的测试运行范围内，考虑到已验证的线圈电绝缘性能，环向场线圈额定电流为25.7 kA，极向场线圈额定电流为+/ -5 kA，所有PS元件均可正常运行。随着综合调试的成功完成，JT-60SA的第一个等离子体成功实现，然后等离子体实验阶段开始。介绍了JT-60SA综合调试中线圈通电试验的重点成果及取得的成果。

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Coil energization tests in JT-60SA integrated commissioning

In 2023, all the coil Power Supply (PS) components of JT-60SA were tested with the corresponding superconducting coils in the integrated commissioning. Initially, the individual coil energization test was carried out to confirm the performance of each coil PS component. Subsequently, the integrated coil energization test was performed step by step progressively increasing the number of superconductive coils in simultaneous operation. As a result, it was confirmed that, in the tested operation range of Operation-1 phase in 2023, set at the rated current of 25.7 kA for toroidal field coils and +/–5 kA for poloidal field coils considering the validated electrical insulating performance of the coils, all the PS components could be operated as expected. Following the successful completion of the integrated commissioning, the first plasma of JT-60SA was successfully achieved and then the plasma experiment phase started. In this paper, the highlighted results of coil energization tests in JT-60SA integrated commissioning and the achievements were reported.

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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.