Design and Qualification of Joints for ITER Magnet Busbar System

Ilyin, Y.; Gung, C. Y.; Wen, Xinjie; Beemsterboer, C.; Farek, Jaromir; Chen, Liu; Ding, Kaizhong; Lü, Kun; Su, Meini; Chen, Yonghua; Sato, Naoyuki; Clayton, N.; Devred, A.; Mitchell, N.

doi:10.1109/tasc.2016.2515984

Cited by 11 publications

(6 citation statements)

References 7 publications

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“…By this strategy, the twin boxes can be bonded together at room temperature and no heating process so that the bonding quality is easy to control and no flux pollution during the installation process. This connection process was qualified and already applied to the onsite joints installation [7,8].…”

Section: Special Connection Processes For Superconducting Jointmentioning

confidence: 99%

Correction coil and magnet feeder lessons learned

Lu,

Liu,

Wei

et al. 2024

Nucl. Fusion

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China has contributed to the manufacturing of the Error Field Correction Coils (CC) and the Magnet Feeders for ITER (International Thermonuclear Experimental Reactor). The manufacturing projects have been carried by ASIPP (Institute of Plasma Physics Chinese Academy of Sciences). In this paper, the lessons learned from these two manufacturing projects will be described with special focus on some key manufacturing processes. These experiences gained from the work carried so far in correction coil and magnet feeder manufacturing and testing are very valuable not only for the remaining manufacturing tasks of these two projects, but also for similar systems of other Tokamak fusion device.

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Section: Special Connection Processes For Superconducting Jointmentioning

confidence: 99%

Correction coil and magnet feeder lessons learned

Lu,

Liu,

Wei

et al. 2024

Nucl. Fusion

Self Cite

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“…× 33%)), which is less than the criteria for an overall resistance of 3 nΩ at 4 K [1]. Thus, this method is useful to check major distributed degradation, such as the air gap due to the misalignment of the joint boxes at any step before cooling or even at the training of the joint assembly.…”

Section: Dependence Of Contact Resistance On the Electric Potential P...mentioning

confidence: 99%

“…An ITER toroidal coil (TFC) is electrically connected to the 68-kA main busbar of a feeder (terminal joint), as shown in Fig. 1 [1,2]. A large electrical contact resistance leads to severe consequences, such as magnet quenching and arc discharge.…”

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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“…The design of the PF joints is based on the twin-box layout [10][11][12][13][14][15][16][17][18] either in the 'shaking hands' or in the 'praying hands' configuration [19]. The two NbTi cables are connected by a saddle composed of two copper soles soldered together with a copper shim in between to relax the tolerances of the assembly [20].…”

Section: Introductionmentioning

confidence: 99%

“…Inside the box, the Ni/Cr coating is removed from the strands at the cable terminations. The strands are soldered to the copper sole, thus reducing the overall electrical resistance of the joint [19,20].…”

Section: Introductionmentioning

confidence: 99%

Performance review of the joints for the ITER poloidal field coils

Breschi

Cavallucci

Adeagbo

et al. 2023

Supercond. Sci. Technol.

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For large scale magnets wound with cable-in-conduit conductors, the safe operation of the joints is of paramount importance to guarantee adequate reliability and stability margin of the whole magnet. For this reason, during the R&D activities undertaken for the development of the ITER magnet system, several experimental campaigns were launched to study the AC and DC performance of the joint and limit the risk of thermal runaways at the joints during the tokamak operation. The joint electrical resistance must be limited below specified values to avoid excessive heating generated by the transport current. Moreover, in presence of time-varying fields, different type of losses arise at the joints, which can be associated to their superconducting and resistive parts. The relative importance of these losses depends on the joint manufacturing solution. The aim of this investigation is to analyse the performance at different working conditions of the joints for the connection of the conductors of the Poloidal Field (PF) coils of the ITER magnet system.This work presents, for the first time, a wide review of the test campaign performed from 2016 to 2021 on the PF joint samples during the three manufacturing phases, namely pre-qualification, qualification and production. The values of electrical resistances and losses under sinusoidal field variations are reported in the paper at different operating conditions, thus building a useful database to assess the joint performances during the machine operation. The data here collected show the impact of the manufacturing techniques on the joint performances and, furthermore, represent a useful tool for the validation of numerical and analytical models of joints.

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Design and Qualification of Joints for ITER Magnet Busbar System

Cited by 11 publications

References 7 publications

Correction coil and magnet feeder lessons learned

Correction coil and magnet feeder lessons learned

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

Performance review of the joints for the ITER poloidal field coils

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