Design and Analysis of Full Size Joint Sample for ITER PF Coil

被引:0
作者
Y. Yao
Y. T. Song
H. Wu
X. Y. Huang
G. Shen
B. Hu
L. Wang
X. D. Zheng
机构
[1] Chinese Academy of Sciences,Institute of Plasma Physics
来源
Journal of Fusion Energy | 2015年 / 34卷
关键词
PF coil; Joint; NbTi superconductor; Electromagnetic analysis; Mechanical analysis;
D O I
暂无
中图分类号
学科分类号
摘要
Joints are essential components of poloidal field coil in fusion device, serving as an electric and coolant transfer between adjacent superconductors. The design of full size joint sample has been carried out by ASIPP. In the future, this sample will be tested in the Sultan facility at Villigen. The test contents include joint total resistance at 4.2 K and 55 kA with 2 T external field, and AC losses at 4.2 K and 45 kA with an external field varying from 0 to 2 T in 1 s. This paper mainly describes the design and analysis of full size joint sample. This sample is composed of two single conductor legs, a praying-hand joint to be placed in the high field, and two terminals to be connected to the transformer of the test facility. The temperature sensors and voltage taps are used for measuring and calculating the DC resistance and AC loss. In order to support the design, the electromagnetic and mechanical analyses are performed. According to the electromagnetic and mechanical analyses, the results show that this design is feasible.
引用
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页码:802 / 807
页数:5
相关论文
共 45 条
[1]  
Simon F(2012)Design of the ITER PF coil joints IEEE Trans. Appl. Supercond. 22 4804104-426
[2]  
Boyer C(2010)Reliability considerations for the ITER poloidal field coils IEEE Trans. Appl. Supercond. 20 423-1169
[3]  
Ilyin Y(2003)Design and manufacture of a prototype NbTi full-size joint sample for the ITER poloidal field coils Fusion Eng. Des. 66–68 1165-263
[4]  
Beemsterboer C(2013)Technology and tooling to manufacture low-ohm (<2 nΩ) electrical joints of the ITER PF1 coil IEEE Trans. Appl. Supercond. 23 4201605-27
[5]  
Lim BS(2005)A low cost joint for the ITER PF coils, design and test results Fusion Eng. Des. 75–79 259-127
[6]  
Simon F(2005)Modeling AC losses in the ITER NbTi poloidal field full size joint sample (PF-FSJS) using the THELMA code Fusion Eng. Des. 75–79 23-426
[7]  
Ilyin Y(2005)Design and manufacture of a full size joint sample (FSJS) for the qualification of the poloidal field (PF) insert coil IEEE Trans. Appl. Supercond. 15 1379-undefined
[8]  
Lim BS(2001)Joints for large superconducting conductors Fusion Eng. Des. 58–59 123-undefined
[9]  
Cau F(2009)Calorimetric method for current sharing temperature measurements in ITER conductor samples in SULTAN Fusion Eng. Des. 84 423-undefined
[10]  
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