Published October 2014 | Version v1
Report Open

Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor

  • 1. National Inst. for Fusion Science, Toki, Gifu (Japan)
  • 2. Tohoku Univ., Graduate School of Engineering, Dept. of Quantum Science and Energy Engineering, Sendai, Miyagi (Japan)
  • 3. Graduate Univ. for Advanced Studies, Toki, Gifu (Japan)

Description

Innovative winding method by connecting high-temperature superconducting (HTS) conductors enables efficient construction of the helical fusion reactor FFHR-d1. A large-current capacity HTS conductor is being developed by incorporating a number of innovative ideas, such as simple stacking of the state-of-the-art YBCO tapes embedded in a copper jacket, surrounded by electrical insulation inside the conductor, and the outer stainless-steel jacket cooled by gas helium. A prototype conductor has reached a current of 100 kA at a bias magnetic field of 5.3 T and temperature of 20 K. A 100 kA current was successfully sustained for 1 hour at 4 K. A low-resistance bridge-type mechanical lap joint is being developed and the sample conductor confirmed a 2 nΩ resistance in the experiment. (author)

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Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
NIFS--1106

Conference

Title
25. IAEA Fusion Energy Conference
Dates
13-18 Oct 2014
Place
Saint Petersburg (Russian Federation)

Optional Information

Notes
26 refs., 7 figs.
Secondary number(s)
IAEA-CN--221; FIP/P--8-21