Superconducting magnet operation in JT-60SA integrated commissioning test

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

Fusion Engineering and Design Pub Date : 2025-03-20 DOI:10.1016/j.fusengdes.2025.114946

Kazuya Hamada , Haruyuki Murakami , Kazuma Fukui , Katsumi Kawano , Yoshihiro Onishi , Katsutomi Usui , Yoshitoshi Kashiwa , Atsushi Honda , Hisashi Ichige , Minoru Sato , Taichi Abe , Ryota Sakurai , Masahide Iguchi , Katsuhiko Tsuchiya , Kiichi Ohtsu , Katsuhiro Shimada , Shoichi Hatakeyama , Kunihito Yamauchi , Akihiko Isayama , Koji Takahashi , Christine Hoa

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引用次数: 0

Abstract

JT-60SA is a superconducting tokamak experiment device constructed in 2021. The first integrated commissioning (IC) tests in 2021 were interrupted due to an electrical short at the EF1 terminals caused by local weak electrical insulation. Terminal joint repairs, insulation reinforcements, and high-voltage tests took two years. In 2023, the IC test was resumed. The TF coils reached their nominal current of 25.7 kA with a stored energy of about 1 GJ. The 18 TF coils, central solenoid (CS), and six equilibrium field (EF) coils safely passed a fast discharge test to qualify the magnet protection system and the cryogenic system's recovery procedure. The plasma experiments began after individual and combination coil tests. In the plasma experiment, CS and EF coils operated only up to ±5 kA, much lower than their nominal current to stay within the limits of present withstand voltage performance. However,JT-60SA achieved the first plasma and a maximum plasma current of 1.2 MA. It was confirmed that the magnet's mechanical behavior was as expected. The cryogenic system operated stably. This paper describes the results of the magnet system operation and its impact on the cryogenic system.

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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.