Plasma and Fusion Research
Volume 9, 3405086 (2014)
Regular Articles
- Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, 6-6-01-2 Aramaki-Aza-Aoba, Aoba-ku, Sendai, Miyagi 980-8579, Japan
- 1)
- National Institute for Fusion Science, 322-6 Oroshi-cho, Toki, Gifu 509-5292, Japan
- 2)
- The Graduate University for Advanced Studies, 322-6 Oroshi-cho, Toki, Gifu 509-5292, Japan
Abstract
In this paper, we reported design, fabrication and test of a prototype 100-kA-class high-temperature superconducting (HTS) conductor, especially for joint section, to be used for segmented HTS helical coils in the FFHR-d1 heliotron-type fusion reactor. The conductor has a geometry of three rows and fourteen layers of Gadolinium Barium Copper Oxide HTS (GdBCO) tapes embedded in copper and stainless steel jackets and has a joint section with bridge-type mechanical lap joint. We introduced improved method to fabricate the joint based on pilot experiments and we were able to apply a current of ∼ 120 kA at 4.2 K, 0.45 T to the sample without quench at joint. The obtained joint resistance was ∼ 2 nΩ, which was lower than our previous data. Though joint resistance increased with a rise in current and magnetic field, predicted joint resistance in the environment of actual helical coil in the FFHR-d1 was small enough to properly run the cryoplant of the reactor.
Keywords
high-temperature superconductor (HTS), REBCO, fusion reactor, helical reactor, FFHR-d1, mechanical joint, joint resistance, remountable HTS magnet, segmented HTS magnet
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This paper may be cited as follows:
Satoshi ITO, Yutaro SEINO, Nagato YANAGI, Yoshiro TERAZAKI and Akio SAGARA, Plasma Fusion Res. 9, 3405086 (2014).