Paper

21.7-T Large-Scale High-Temperature Superconducting Toroidal Magnet for Tokamak Fusion Application

Volume Number:
35
Issue Number:
6
Pages:
1
–
6
Publication Date:
June 2025
Li, Z. Y. and Pan, Z. C. and Yang, H. G. and Li, Y. Y. and Cao, Y. J. and Qiao, L. and Gao, B. and Huang, G. and Zhang, C. and Zhu, K. P. and Zhao, Y. S. and Chen, K. F. and Zhou, J. Q. and Yao, L. and Wei, Q. Q. and Guo, Y. X. and Liu, Y. Y. and Huang, Y. and Qiao, H. and Chen, W. J. and Du, Y. Q. and Zhang, K. and Chen, X. and Gong, A. H. and Dong, G. and Ye, Y. M. and Yang, Z.

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Abstract

With the rapid advancement of magnetic confinement fusion technology, high-temperature superconductors (HTS) have emerged as a cornerstone for compact and efficient tokamak systems due to their exceptional current-carrying capacity under high magnetic fields. Against this backdrop, energy singularity fusion power technology (ES Company) initiated the JingTian (JT) magnet project in December 2023 to validate the toroidal field magnet design for its next-generation all-HTS tokamak facility, HH170. Prior to the HH170 project, ES Company developed and constructed the world’s first all-HTS tokamak. This facility successfully achieved its first plasma operation in June 2024, marking a significant milestone in fusion technology (Z. Yang et al., 2024; Z. Y. Li et al., 2024). This article details the design, fabrication, and performance testing of the JT magnet, a large-scale D-shaped winding pack comprising 32 modular rareearth barium copper oxide (ReBCO) based pancake coils. Operating at 5 K with supercritical helium cooling, the JT magnet achieved a record-breaking peak magnetic field of 21.7 T, the highest reported for an all-HTS tokamak magnet. Steady-state operation at 24.3 kA confirmed its structural integrity, cryogenic cooling efficiency, and alignment with magnetic field modeling predictions. The success of the JT magnet not only provides critical data for the HH170 design but also establishes a foundational milestone for the engineering application of high-field compact tokamaks, demonstrating significant potential to reduce fusion reactor size and cost.