High temperature superconductors for the ITER magnet system and beyond

Fietz, W.H.; Fink, S.; Heller, R.; Komarek, P.; Tanna, V.L.; Zahn, G.; Pásztor, G.; Wesche, R.; Salpietro, E.; Vostner, A.

doi:10.1016/j.fusengdes.2005.06.198

Cited by 32 publications

(17 citation statements)

References 4 publications

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“…They have high critical currents at relatively high temperature (less than 50 K) and that makes it feasible to be cooled by cryocoolers instead of by liquid helium. YBCO had already been proposed to be applied in tokamak magnets in 2004 [4]. Figure 1 shows the electromagnetic characteristics of Bi2223 (made by Innost, China) and YBCO (made by SuperPower, USA) obtained by experiments.…”

Section: Hts Materials May Be Applied In Tokamak Magnetsmentioning

confidence: 99%

Research of HTS application on tokamak magnets

Ren¹,

Deng²,

Xu³

et al. 2015

Proceedings of the 2015 International Conference on Power Electronics and Energy Engineering

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Abstract-in this paper, the application feasibility of HTS tapes on tokamak magnets is discussed and the existing four kinds of HTS high current conductors are summarized. Furthermore, an YBCO conductor structure suitable for a 10 GJ tokamak TF magnet is designed and the current carrying capacity is evaluated. The simulation result shows that the critical current of the YBCO conductor is about 75 kA @ 10 T, 30 K.

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Section: Hts Materials May Be Applied In Tokamak Magnetsmentioning

confidence: 99%

Research of HTS application on tokamak magnets

Ren¹,

Deng²,

Xu³

et al. 2015

Proceedings of the 2015 International Conference on Power Electronics and Energy Engineering

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“…Among them, the ITER and the GSI/FAIR project will require leads operating in both DC and pulsed mode [11], [12].…”

Section: Other Large Capacity Current Leadsmentioning

confidence: 99%

Large-capacity current leads

Ballarino

2008

Physica C: Superconductivity

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Feeding superconducting magnets with reliable low-loss devices is a key issue for any cryo-electrical system. Conventional or HTS current leads can be used, and cooling methods, materials, and geometries can be chosen to optimize the thermo-electrical performance of the system. The LHC magnets are powered via more than 3000 current leads transporting altogether about 3 MA of current. With thousands of leads, the LHC lead project represents today the largest project of its kind ever undertaken. Following a review of the LHC lead project, an overview of the choices that can be made for the optimization of large capacity current leads is presented. Examples are given of other leads for large scale magnet systems for which the use of HTS is being envisaged.

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“…The production of largescale HTS magnets for use in fusion reactors has also been considered [2,3]. Though it is still widely believed that HTS materials are fragile, it is actually possible to fabricate strong coils using rare-earth barium copper oxide (RE-BCO) tape.…”

Section: Introductionmentioning

confidence: 99%

Feasibility of HTS Magnet Option for Fusion Reactors

Yanagi

Terazaki

Natsume

et al. 2014

Plasma and Fusion Research

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Conceptual design studies are being carried out on the application of high-temperature superconducting (HTS) conductors and coils to the magnet systems of fusion reactors. A 100-kA-class HTS conductor is required to be applied at high magnetic fields of > 12 T. A simple stack of YBCO tapes embedded in copper and stainless-steel jackets is found to be a practical approach to producing large-scale conductors that exhibit high cryogenic stability and mechanical rigidity. The feasibility of the segmented fabrication method for large complex HTS coils, such as the helical coils in the LHD-type helical fusion reactor FFHR-d1, is being investigated by developing mechanical bridge-type lap joint technology of HTS conductors.

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High temperature superconductors for the ITER magnet system and beyond

Cited by 32 publications

References 4 publications

Research of HTS application on tokamak magnets

Research of HTS application on tokamak magnets

Large-capacity current leads

Feasibility of HTS Magnet Option for Fusion Reactors

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