Results of All ITER TF Full-Size Joint Sample Tests in Japan

被引:2
|
作者
Kajitani, Hideki [1 ]
Imagawa, Shinsaku [2 ]
Obana, Tetsuhiro [3 ]
Takada, Suguru [4 ]
Hamaguchi, Shinji [2 ]
Chikaraishi, Hirotaka [3 ]
Nakamoto, Mio [5 ]
Yamane, Minoru [5 ]
Yoshizawa, Kazumi [5 ]
Uno, Yasuhiro [5 ]
Matsui, Kunihiro [5 ]
Koizumi, Norikiyo [5 ]
Nakahira, Masataka [5 ]
机构
[1] Natl Inst Quantum & Radiol Sci & Technol, Naka, Ibaraki 3110193, Japan
[2] Natl Inst Fus Sci, Dept Hel Plasma Res, Toki, Gifu 5095292, Japan
[3] Natl Inst Fus Sci, Toki, Gifu 5095292, Japan
[4] NIFS, Large Hel Device, Toki, Gifu 5095292, Japan
[5] QST, Naka, Ibaraki 3110193, Japan
关键词
ITER TF coil; TF joint; joint resistance;
D O I
10.1109/TASC.2021.3064004
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
Nine toroidal field (TF) coils have been developed in Japan for the international thermonuclear experimental reactor (ITER). The joint resistance of TF coil should satisfy the requirement of smaller than 3 nano-ohm at 2 T of external magnetic field and 68 kA of transport current. Full-size joint sample (FSJS) tests were performed for joint development and for TF coil manufacture, as part of the process control. 11 FSJS tests are conducted in total. FSJS tests were conducted with assistance from a test faculty in the National Institute for Fusion Science as reported in a previous paper. All FSJS tests successfully satisfied the requirement of resistance less than 3 n Omega at 2 T. Additionally, the TF coil joints are subjected to cyclic electromagnetic force and warm-up/cool-down during the ITER operation. The authors investigated the joint performance for the abovementioned influence. The results showed no degradation in the joint resistance. Thus, the TF joint developed in Japan was qualified successfully.
引用
收藏
页数:5
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