New Inspection Method of Soldering Region at Room Temperature for ITER TF Termination

Kajitani, Hideki; Nakamoto, Mio; Kasai, Yuma; Yamane, Minoru; Matsui, K.; Koizumi, N.

doi:10.1109/tasc.2019.2899661

Cited by 5 publications

(8 citation statements)

References 9 publications

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“…VT12, VT34, and VT56 are described as round, triangle, and rectangle points, respectively. The reason for the difference between these VTs is described in [4]. All of the joint resistances could be below 3 nΩ in both Figs.…”

Section: Amentioning

confidence: 92%

“…A brief explanation of the FSJS test method is provided in this section based on the details shown in [4]. An FSJS fabricated by TF coil manufacturers is installed in the NIFS test facility, and copper busbars attached to the upper joint are connected to the current leads of the test facility.…”

Section: Test Methodsmentioning

confidence: 99%

“…For each TF coil, it is necessary to achieve a sufficiently low joint resistance of less than 3 nΩ for each of the 6 inter-DP joints and 4 nΩ for each of the 2 terminal busbar joints with an external field of 2 T and a transport current of 68 kA. For real TF joint, the soundness of the joint resistance was evaluated at room temperature according to previous studies [3] [4]. In addition to these evaluations, full-size joint sample (FSJS) tests were also performed as a process control in the TF coil fabrication.…”

mentioning

confidence: 99%

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

Kajitani

Imagawa

Obana

et al. 2021

IEEE Trans. Appl. Supercond.

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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 nΩ 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.

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Section: Amentioning

confidence: 92%

Section: Test Methodsmentioning

confidence: 99%

mentioning

confidence: 99%

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

Kajitani

Imagawa

Obana

et al. 2021

IEEE Trans. Appl. Supercond.

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“…In addition, the contact resistance in the TFC double pancake joint (DPJ) was inspected during winding pack (WP) manufacturing [3,4]. The electric potential distribution along the DPJ was measured using electrical Fig.…”

Section: Introductionmentioning

confidence: 99%

“…The electric potential distribution along the DPJ was measured using electrical Fig. 2 Different current path in (a) DPJ [3] and (b) terminal joint.…”

Section: Introductionmentioning

confidence: 99%

Electric Potential Profile with Distributed Degradation in the Terminal Joint for ITER TF Coil System

HASEGAWA,

KAJITANI,

UNO

et al. 2024

Plasma and Fusion Research

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ITER toroidal field coils are electrically connected to 68-kA main busbars (terminal joints). We propose the measurement of the electric potential distribution in a terminal joint using electrical probes (e-probe method) to inspect the contact resistance in the joint. In this study, we experimented with a mockup of a terminal joint. The test current was 20 A, and the electric potential was measured using the e-probe method at room temperature and 77 K. Nine different degradation patterns were prepared by distributing polyimide films in the joint interface. Next, we performed finite element analysis to investigate the detailed relationship between the electric potential distribution and contact resistance at 300 K and 77 K. In the numerical analysis, the same degradation patterns and test current as in the experiment were assumed. The analysis results agree with the experimental results. Different degradation patterns exhibit different electric potential profiles with 10-µV-scale differences. The analysis results also indicate that the e-probe method works when the contact resistance in the degraded area is larger than 1.0 × 10 −5 Ωmm 2 at 77 K and 300 K. c

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Manufacturing of ITER Toroidal Field Coil in Japan

Koizumi

Nakahira

2020

TEION KOGAKU

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The ITER superconducting magnet system consists of 18 toroidal field (TF) coils, six central solenoid (CS) modules, six poloidal field (PF) coils and 18 correction coils. The National Institutes for Quantum and Radiological Science and Technology (QST), serving as the Japan Domestic Agency (JADA) in the ITER project, is responsible for the procurement of nine TF coils. Manufacturing of the first TF coil began in October 2013 and was completed in January 2020. While the basic technology for TF coil manufacturing has been developed through large-scale qualification trials, many additional issues were found when developing the first TF coil. Accordingly, these technical issues resolved and the TF coil was successfully completed.The technical issues and their solutions are reported in these special issues.

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New Inspection Method of Soldering Region at Room Temperature for ITER TF Termination

Cited by 5 publications

References 9 publications

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

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

Electric Potential Profile with Distributed Degradation in the Terminal Joint for ITER TF Coil System

Manufacturing of ITER Toroidal Field Coil in Japan

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