First AC loss test and analysis of a Bi-2212 Cable-in-Conduit Conductor for Fusion application
First AC loss test and analysis of a Bi-2212 Cable-in-Conduit Conductor for Fusion application
复制标题
用于融合应用的 Bi-2212 电缆导管导体的首次交流损耗测试和分析
DOI：
10.1088/1361-6668/aa94b8
复制
发表时间：
2017
影响因子：
3.6
通讯作者：
Arnaud Devred
中科院分区：
文献类型：
--
作者：
Jinggang Qin;Yi Shi;Yu Wu;Jiangang Li;Qiuliang Wang;Yuxiang He;Chao Dai;Fang Liu;Huajun Liu;Zhehua Mao;Arend Nijhuis;Chao Zhou;Arnaud Devred
The main goal of the Chinese fusion engineering test reactor (CFETR) is to build a fusion engineering tokamak reactor with a fusion power of 50–200 MW, and plan to test the breeding tritium during the fusion reaction. This may require a maximum magnetic field of the central solenoid and toroidal field coils up to 15 T. New magnet technologies should be developed for the next generation of fusion reactors with higher requirements. Bi 2 Sr 2 CaCu 2 O x (Bi2212) is considered as a potential and promising superconductor for the magnets in the CFETR. R&D activities are ongoing at the Institute of Plasma Physics, Chinese Academy of Sciences for demonstration of the feasibility of a CICC based on Bi2212 round wire. One sub-size conductor cabled with 42 wires was designed, manufactured and tested with limited strand indentation during cabling and good transport performance. In this paper, the first test results and analysis on the AC loss of Bi2212 round wires and cabled conductor samples are presented. Furthermore, the impact of mechanical load on the AC loss of the sub-size conductor is investigated to represent the operation conditions with electromagnetic loads. The first tests provide an essential basis for the validation of Bi2212 CICC and its application in fusion magnets.
