R&D Activities of Joint Manufacture for ITER Poloidal Field Coil

被引：0
|
作者：
Yao Yao [1 ]
Song Yuntao [1 ]
Huang Xiongyi [1 ]
Shen Guang [1 ]
Wu Huan [1 ]
Wang Lin [1 ]
Hu Bing [1 ]
Luo Zhiren [1 ]
机构：
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Peoples R China
来源：
PLASMA SCIENCE & TECHNOLOGY | 2015年 / 17卷 / 07期
基金：
中国国家自然科学基金;
关键词：
PF coil; joint; structural analysis; thermal analysis; DESIGN;
D O I：
10.1088/1009-0630/17/7/15
中图分类号：
O35 [流体力学]; O53 [等离子体物理学];
学科分类号：
070204 ; 080103 ; 080704 ;
摘要：
Electrical joints are critical components of the PF coil in the tokamak, serving as an electric and coolant transfer between adjacent conductors. The technologies and tooling used for joint manufacture are great challenges in coil fabrication, including termination box and cover manufacturing, jacket removal of the conductor, petals drawing apart and reformation, nickel coating removal and tin plating on the cable, compaction of the cable into the termination, final machining of the termination, etc. This paper mainly focuses on the solution of technical issues, based on previous R&D activities of joint. Meanwhile, a detailed manufacture plan has been confirmed. The technologies and tooling also can be used as reference for the electrical joint manufacture for PF coils and other large-scale coils.
引用
收藏
页码：612 / 616
页数：5
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