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Title: High-performance superconductors for Fusion Nuclear Science Facility

High-performance superconducting magnets play an important role in the design of the next step large-scale, high-field fusion reactors such as the fusion nuclear science facility (FNSF) and the spherical tokamak (ST) pilot plant beyond ITER. Here, Princeton Plasma Physics Laboratory is currently leading the design studies of the FNSF and the ST pilot plant study. ITER, which is under construction in the south of France, utilizes the state-of-the-art low temperature superconducting magnet technology based on the cable-in-conduit conductor design, where over a thousand multifilament Nb 3Sn superconducting strands are twisted together to form a high-current-carrying cable inserted into a steel jacket for coil windings. We present design options of the high-performance superconductors in the winding pack for the FNSF toroidal field magnet system based on the toroidal field radial build from the system code. For the low temperature superconductor options, the advanced J cNb 3Sn RRP strands (J c > 1000 A/mm 2 at 16 T, 4 K) from Oxford Superconducting Technology are under consideration. For the high-temperature superconductor options, the rectangular-shaped high-current HTS cable made of stacked YBCO tapes will be considered to validate feasibility of TF coil winding pack design for the ST-FNSF magnets.
ORCiD logo [1] ;  [1] ; ORCiD logo [2] ;  [2]
  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. Univ. of Geneva, Geneva (Switzerland)
Publication Date:
Report Number(s):
Journal ID: ISSN 1051-8223; TRN: US1701274
Grant/Contract Number:
Accepted Manuscript
Journal Name:
IEEE Transactions on Applied Superconductivity
Additional Journal Information:
Journal Volume: 27; Journal Issue: 4; Journal ID: ISSN 1051-8223
Institute of Electrical and Electronics Engineers (IEEE)
Research Org:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Org:
Contributing Orgs:
Univ Geneva, Dept Condensed Matter Phys, CH-1205 Geneva, Switzerland
Country of Publication:
United States
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; material radiation limits; next-step fusion reactors; superconducting fusion magnet design; cable-in-conduit conductors
OSTI Identifier: