Conceptual Design of the CFETR Toroidal Field Superconducting Coils

被引：3

作者：

Zheng, J. X. ^{[1
]}

Song, Y. T. ^{[1
]}

Liu, X. F. ^{[1
]}

Li, J. G. ^{[1
]}

Wan, Y. X. ^{[1
]}

Wan, B. N. ^{[1
]}

Lei, M. Z. ^{[1
]}

Zhu, C. X. ^{[2
]}

Kang, R. ^{[2
]}

Khan, S. U. ^{[2
]}

机构：

[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China

[2] Univ Sci & Technol China, Hefei 230015, Peoples R China

来源：

IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY | 2015年 / 25卷 / 02期

关键词：

China Fusion Engineering Test Reactor (CFETR); magnet; superconducting; toroidal field (TF);

D O I：

10.1109/TASC.2015.2396942

中图分类号：

TM [电工技术]; TN [电子技术、通信技术];

学科分类号：

0808 ; 0809 ;

摘要：

The China Fusion Engineering Test Reactor (CFETR) superconducting tokamak is a national scientific research project of China with plasma major and minor radii of 5.7 and 1.6 m, respectively. The magnetic field in the center of plasma at a radius of R = 5.7 m is 5.0 T. The major objective of the project is to build a fusion engineering tokamak reactor with fusion power within the range of 50-200 MW and should be self-sufficient by blanket. Sixteen toroidal field (TF) superconducting coils of CFETR have been arrayed toroidally and are made up of Nb3Sn superconductor. The maximum magnetic field of the TF coil is 10.8 T under the operation current of 67.4 kA. The TF coil should have strong stability margin under the condition of high field and strain. This paper discusses the design parameters, electromagnetic distribution, structure, and thermal and stability analysis of the TF superconducting magnet for CFETR.

引用

页码：1 / 9

页数：9

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