高温超导托卡马克红黄70的设计、调试和首次运行

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-07-22 DOI:10.1016/j.fusengdes.2025.115341

Z. Yang, Y.J. Cao, B. Chen, G.B. Chen, W.J. Chen, G. Dong, Y.Q. Du, H.Y. Guo, Y.X. Guo, Y. Hua, Y. Huang, Y.Y. Li, Z.Y. Li, J.H. Liu, J.Q. Ma, Z.C. Pan, H. Qiao, Y.Z. Wang, Q.Q. Wei, H.G. Yang, Y.J. Zhu

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引用次数: 0

摘要

红黄70 （HH70）是世界上第一个全高温超导托卡马克（HTS）。这是一个中等尺寸的托卡马克，宽高比适中，主要半径为R0 = 0.7 m，次要半径为a = 0.25 - 0.3 m。在设计线圈工作温度为20 K时，磁体线圈上的最大设计磁场为Bmax = 2.5 T，等离子体中心环向磁场B0 = 0.6 T。HH70的线圈包括中心螺线管（CS）、极向场（PF）线圈和环向场（TF）线圈均以稀土钡氧化铜（ReBCO） HTS带为主要载流元件。HH70的建造和组装于2024年完成。试验结果表明，高温超导线圈的性能与工程仿真结果基本一致。综合调试验证了配套子系统的能力。本文回顾了HH70托卡马克的设计、装配、调试和初始运行，包括其高温超导线圈和主要支撑系统。HH70的成功运行证明了全高温托卡马克的可行性，提供了宝贵的工程经验。

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Design, commissioning, and first operation of the high-temperature superconducting tokamak Honghuang70

Honghuang70 (HH70) is the world’s first fully high-temperature superconducting (HTS) tokamak. It is a medium-sized tokamak with modest aspect ratio, featuring a major radius of R₀ = 0.7 m and a minor radius a = 0.25 - 0.3 m. At the designed coil operation temperature of 20 K, the maximum designed magnetic field on the magnet coils is B_max = 2.5 T, and the toroidal magnetic field at the plasma center B₀ = 0.6 T. All of HH70’s coils including the central solenoid (CS), the poloidal field (PF) coils and the toroidal field (TF) coils are constructed with the rare-earth barium copper oxide (ReBCO) HTS tape as the main current-carrying component. The construction and assembly of HH70 were completed in 2024. The coil commissioning results show that the behavior of the HTS coils agrees with engineering simulation results. The integrated commissioning has verified the capability of the supporting subsystems. This paper reviews the design, assembly, commissioning and initial operation of the HH70 tokamak, including its HTS coils and main supporting systems. The successful operation of HH70 demonstrates the feasibility of full-HTS tokamaks and provides valuable engineering experience.

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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.