铜管压实下高柔性 REBCO 电缆临界电流的实验研究

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Haihong Liu , Huan Jin , Guanyu Xiao , Le wang , Yongsheng Wu , Fang Liu , Chao Zhou , Xiaochuan Liu , Jinggang Qin
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引用次数: 0

摘要

中国科学院等离子体物理研究所(ASIPP)正在开发用于下一代核聚变装置中央螺线管(CS)线圈的大电流 REBCO 电缆导体(CICC)。子电缆作为 CICC 中的关键部件,在确保整个 CS 线圈系统的机械支撑强度和载流稳定性方面发挥着举足轻重的作用。因此,本文首次开发了一种工艺,通过将高柔性 REBCO 电缆(HFRC)插入铜管并压实,制成符合要求的副电缆。同时,利用实验方法在 77 K 和自场条件下对该工艺的可行性和可靠性进行了评估和优化。结果表明,没有铜带保护的子电缆的临界电流(IC)下降了 25.42%。相反,如果在高频无线电子电缆和铜管内壁之间使用至少一层铜带保护层作为保护缓冲,则压实后的临界电流(IC)在 1%的误差范围内保持稳定。这些发现证明了这种子电缆制备工艺的可行性。同时,这种压实方法为未来磁体应用中全尺寸导体的开发奠定了坚实的工艺基础。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Experimental study on the critical current in highly flexible REBCO cables under copper tube compaction
The Institute of Plasma Physics Chinese Academy of Sciences (ASIPP) is developing the high-current REBCO cable-in-conduit conductor (CICC) for use in the Central Solenoid (CS) coil of the next generation nuclear fusion device. The aim is to develop a CICC comprising six REBCO sub-cables to satisfy the requirements of operation with a current of around 46 kA and a peak field of up to 20 T. Sub-cables, as crucial components within CICCs, play a pivotal role in ensuring the mechanical support strength and current-carrying stability of the entire CS coil system. Therefore, a process was developed in this paper for the first time to make a sub-cable that meets the requirements by inserting the Highly Flexible REBCO Cable (HFRC) cable into a copper tube and compacting it. Meanwhile, the feasibility and reliability of this process were evaluated and optimized using experimental methods at 77 K and self-field. The result indicated that sub-cables without copper tape protection experienced a 25.42% degradation in critical current (IC). In contrast, when at least one protective layer of copper tape was used as a protective buffer between the HFRC cable and the inner wall of the copper tube, the IC remained stable within a 1% error margin after compaction. These findings demonstrate the feasibility of this sub-cable preparation process. Meanwhile, this compaction method provides a solid process foundation for the development of full-size conductors in future magnet applications.
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来源期刊
Fusion Engineering and Design
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.
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