Design of the PF system for EAST(HT-7U) tokamak

被引：10

作者：

Wu, WY ^{[1
]}

Li, BZ ^{[1
]}

Zhuning ^{[1
]}

机构：

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

来源：

20TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, PROCEEDINGS | 2003年

关键词：

D O I：

10.1109/FUSION.2003.1426677

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

EAST(HT-7U) superconducting tokamak is an advanced steady-state plasma physics experimental device. The poloidal field(PF) coil system is used with superconducting conductor. The NbTi cable-in-conduit conduct (CICC) cooled by supercritical helium at 4.5 K is chosen as superconductor for all of the PF magnets. It was consisted of fourteen superconducting coils, located symmetrically about the equator plane of the machine. The PF system was supported by the case of TF coils. The final engineering design of PF system will be report in this paper. The maximum capacity of the volt seconds for EAST(Experimental advanced superconducting Tokamak) PF system is about 10 Web and the peak magnetic field in PF coils is about 4.5 T.

引用

页码：436 / 439

页数：4