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Journal Articles

Addressing the technical challenges for the construction of the ITER Central Solenoid

Libeyre, P.*; Bessette, D.*; Jewell, M.*; Jong, C.*; Lyraud, C.*; Rodriguez-Mateos, M.*; Hamada, Kazuya; Reiersen, W.*; Martovetsky, N.*; Rey, C.*; et al.

IEEE Transactions on Applied Superconductivity, 22(3), p.4201104_1 - 4201104_4, 2012/06

 Times Cited Count:6 Percentile:40.45(Engineering, Electrical & Electronic)

The Central Solenoid (CS) of the ITER magnet system will play a major role in tokamak operation, providing not only the major part of the inductive flux variation required to drive the plasma but also contributing to the shaping of the field lines and to vertical stability control. To meet these requirements, the design has been optimised by splitting the CS into six independently powered coils enclosed inside an external structure which provides vertical precompression thus preventing separation of the coils and, additionally, acting as a support to net resulting loads. To ensure that the CS design meets the ITER criteria, several analyses are performed along with a series of R&D trials to qualify the technologies to be used for the manufacture of the conductor, the coils and the structure.

Journal Articles

Fatigue assessment of the ITER TF coil case based on JJ1 fatigue tests

Hamada, Kazuya; Nakajima, Hideo; Takano, Katsutoshi*; Kudo, Yusuke; Tsutsumi, Fumiaki*; Okuno, Kiyoshi; Jong, C.*

Fusion Engineering and Design, 75-79, p.87 - 91, 2005/11

 Times Cited Count:8 Percentile:51.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Key features of the ITER-FEAT magnet system

Okuno, Kiyoshi; Bessette, D.*; Ferrari, M.*; Huguet, M.*; Jong, C.*; Kitamura, Kazunori*; Krivchenkov, Y.*; Mitchell, N.*; Takigami, Hiroyuki*; Yoshida, Kiyoshi; et al.

Fusion Engineering and Design, 58-59, p.153 - 157, 2001/11

 Times Cited Count:2 Percentile:20.38(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Updating the design of the poloidal field coils for the ITER magnet system

Yoshida, Kiyoshi; Takahashi, Yoshikazu; Jong, C.*; Bessette, D.*; Mitchell, N.*

no journal, , 

The ITER magnet system consists of 18 TF coils, 6 PF coils, 6 CS modules, 18 CC and their feeders. Because of the difficulties in replacing the PF coils, the most unreliable component (the coil insulation) is designed with extra redundancy. There are two insulation layers with a thin metal screen in between. By monitoring the voltage of the intermediate screen, it is possible to detect an incipient short, defined as a short in only one of the two insulation layers. Alternately the faulty double pancake must be disconnected and by-passed because PF conductor uses NbTi strand. This implies that the remaining pancakes are operated at a higher current as the backup mode. Jumpers are pre-installed on the coil surface to allow this reconnection with a minimum of works in the cryostat and the conductor is designed with an extra margin. This paper presents the latest design for by-pass operation in PF coil, and thermal analysis of its conductor for the backup mode. The PF coil has an enough design margin for normal and backup mode.

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