Concept design of the CFETR central solenoid
Concept design of the CFETR central solenoid
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DOI：
10.1016/j.fusengdes.2014.12.018
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发表时间：
2015-02
影响因子：
1.7
通讯作者：
J. Zheng;Yuntao Song;Xufeng Liu;Jian-gang Li;Y. Wan;B. Wan;M. Ye;Wu Huan
中科院分区：
文献类型：
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作者：
J. Zheng;Yuntao Song;Xufeng Liu;Jian-gang Li;Y. Wan;B. Wan;M. Ye;Wu Huan
中国聚变工程试验堆（CFETR）超导托卡马克是我国的国家级科研项目，其长、短半径分别为5.7 m和1.6 m。半径为5.7 m的等离子体中心磁场设定为5.0 T。该项目的主要目标是建造一个聚变工程托卡马克反应堆，聚变功率在50-200兆瓦之间，并应通过包层自给自足。CFETR的六个中心螺线管线圈结构相同，均由Nb_3Sn超导体制成。此外，在等离子体加热阶段，在CS线圈的工作电流下，等离子体区域的杂散场应小于20 Gs。CS线圈的最大磁场为11.9 T。它是由基于等离子体平衡位形的线圈的工作电流计算的。中心螺线管在高磁场和高应变条件下需要有足够的稳定裕度。本文讨论了CFETR用CS超导磁体的设计参数、电磁场分布、结构和稳定性分析。
China Fusion Engineering Test Reactor (CFETR) superconducting tokamak is a national scientific research project of China with major and minor radius is 5.7 m and 1.6 m respectively. The magnetic field at the center of plasma with radius asR= 5.7 m is set to be 5.0 T. The major objective of the project is to build a fusion engineering tokamak reactor with fusion power in the range of 50–200 MW and should be self-sufficient by blanket. Six central solenoid coils of CFETR with same structure are made of Nb3Sn superconductor. Besides, the stray field in plasma area should be less than 20 Gs with the operation current of CS coils for plasma heating phase. The maximum magnetic field of CS coil is 11.9 T. It is calculated by the coils’ operation current based on plasma equilibrium configuration. The central solenoid needs to have enough stability margin under the condition of high magnetic field and strain. This paper discusses the design parameters, electromagnetic distribution, structure and stability analysis of the CS superconducting magnet for CFETR.