Development of ITER-CS model coil terminal assembling by using indium wires

被引：11

作者：

Takahashi, Y ^{[1
]}

Kato, T ^{[1
]}

Nunoya, Y ^{[1
]}

Ando, T ^{[1
]}

Nishijima, G ^{[1
]}

Nakajima, H ^{[1
]}

Hiyama, T ^{[1
]}

Sugimoto, M ^{[1
]}

Isono, T ^{[1
]}

Koizumi, N ^{[1
]}

Kawano, K ^{[1
]}

Tsuji, H ^{[1
]}

机构：

[1] Japan Atom Energy Res Inst, Naka Fus Res Estab, Naka, Ibaraki 3110193, Japan

来源：

FUSION ENGINEERING AND DESIGN | 2001年 / 58-59卷

关键词：

Nb(3)Sn; cable-in-conduit conductor; International Thermonuclear Experimental Reactor (ITER); indium wires; superconducting coils; terminal joint;

D O I：

10.1016/S0920-3796(01)00289-7

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：

The ITER-CS model coil was fabricated and its performance test was successfully carried out. The assembling technique by using indium wires was developed for the terminal joints. The short samples were fabricated to establish the technique and their joint resistance was low enough ( similar to 4 n Omega at 4.5 T, 50 kA). This technique was applied to the assembling of seven joints in the CS model coils and the assembling was successfully completed. It has been confirmed in the performance test that the resistance of these joints is lower than 5 n Omega. According to these results, it can be concluded that the developed assembling technique by using indium wires is applicable and useful to the terminal joints of superconducting coils with the large-current conductors. (C) 2001 Elsevier science B.V. All rights reserved.

引用

页码：93 / 97

页数：5

共 5 条

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