Design and test of superconducting joint for ITER calibration field magnet

doi:10.16568/j.0254-6086.202202006

Nuclear Fusion and Plasma Physics ›› 2022, Vol. 42 ›› Issue (2): 206-206.DOI: 10.16568/j.0254-6086.202202006

• Nuclear Fusion Engineering • Previous Articles Next Articles

Design and test of superconducting joint for ITER calibration field magnet

ZHANG Biao1, ZHENG Jin-xing2, WANG Lin2, LU Kun2, WEI Jing2

(1. School of Mechanical Engineering, Anhui University of Science and Technology, Huainan 232001; 2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031)

Received:2020-04-29 Revised:2021-04-23 Online:2022-06-15 Published:2022-06-17

ITER校正场磁体超导接头的设计与测试

张彪1，郑金星2，王琳2，陆坤2，卫靖2

(1. 安徽理工大学机械工程学院，淮南 232001；2. 中国科学院等离子体物理研究所，合肥 230031)

作者简介:张彪(1995-)，男，江苏徐州人，硕士研究生，从事电物理装置设计研究。
基金资助:
国家自然科学基金(51525703)；中国科学院“青年创新促进会优秀会员”人才项目(Y201979)

Abstract

Abstract: A superconducting connector for ITER correction coil is designed to realize low resistance connection between superconducting cables. The structure of the correction field superconducting joint and superconductor is introduced, the direct resistance of the joint is calculated, and the reasonable manufacturing process is determined. The test resistance of joint sample is 1.4nΩ, lower than the design value of 5nΩ.

Key words: ITER, Superconducting joint, Conductor, Resistance test

摘要： 设计了一种超导接头用于ITER校正场线圈和超导电流引线之间电流和液氦传输。介绍了校正场线圈超导接头和超导体的结构，计算了接头的直流电阻，确定了合理的超导接头制造工艺。超导接头样品电阻的检测值为1.4nΩ，低于5nΩ的设计值。

关键词: ITER, 超导接头, 超导体, 电阻测试

CLC Number:

TL62+7

ZHANG Biao, ZHENG Jin-xing, WANG Lin, LU Kun, WEI Jing. Design and test of superconducting joint for ITER calibration field magnet[J]. Nuclear Fusion and Plasma Physics, 2022, 42(2): 206-206.

张彪, 郑金星, 王琳, 陆坤, 卫靖. ITER校正场磁体超导接头的设计与测试[J]. 核聚变与等离子体物理, 2022, 42(2): 206-206.

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Design and test of superconducting joint for ITER calibration field magnet

ITER校正场磁体超导接头的设计与测试

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