Pre-compression requirements for the ITER Central Solenoid

被引:11
|
作者
Fu, Y. [1 ]
Jong, C.
Michael, P.
Mitchell, N.
机构
[1] ITER Int Team, Naka, Ibaraki 3110193, Japan
[2] ITER Int Team, Garching, Germany
[3] MIT, PSFC, Cambridge, MA USA
关键词
CS coil; ITER; pre-compression;
D O I
10.1109/TASC.2006.873257
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 ITER CS contains 6 identical but electrically independent modules. ITER plasma shaping requirements yield a wide range of radial (or hoop) loads and a wide range of vertical loads on each CS module. Pre-compression is used to maintain contact between the modules during all stages of plasma operation, to minimize primary tensile stresses in the coil insulation, and to prevent toroidal ratcheting of the modules during repeat operation. The preload requirements for the ITER Central Solenoid (CS) are the subject of this paper. Axial pre-compression of CS stack is carefully analyzed using finite element (FE) models. Conflicting requirements on the pre-compression structure (namely, the generation of large axial pre-compression with minimal use of radial space outside the modules) are balanced to support the desired plasma shapes.
引用
收藏
页码:791 / 794
页数:4
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