Cited by 43Superconducting Materials and ApplicationsMagnetic confinement fusion researchFusion materials and technologies

Conceptual magnet design study for fusion nuclear science facility

Open access
Zhai, Yuhu, Titus, Peter, Kessel, Charles, El-Guebaly, Laila·2018·Fusion Engineering and Design

Abstract

Abstract The Fusion Nuclear Science Facility (FNSF) is a nuclear confinement device to provide the integrated fusion environment with fusion reactor components. The FNSF is the stepping stone to bridge the technical gaps of burning plasma and nuclear science between the International Thermal Nuclear Experimental Reactor (ITER), currently under construction in the south of France, and the demonstration power plant (DEMO). For the next-step fusion reactors, resistive copper magnet cannot be a sustainable solution due to large power consumption in coils of large size needed. Both Low temperature superconductor (LTS) and high temperature superconductor (HTS) are considered for the FNSF magnet design based on the state-of-the-art fusion superconducting magnet technology. Input parameters to FNSF magnet design include magnetic field of 7.5 T at plasma center with a major radius of 4.8 m and minor radius of 1.2 m, and a peak field of over 16 T on the TF coils. The high magnetic field can be achieved by using the high performance ternary Restack Rod Process (RRP) Nb3Sn strands for toroidal field (TF) magnets and a high aspect ratio rectangular cable-in-conduit conductor (CICC) design. The conductor design concept and TF coil winding pack composition and dimension are discussed based on the horizontal maintenance scheme. Neutron radiation limits for the LTS and HTS conductors and electrical insulation materials are reviewed based on the available materials previously tested. The material radiation limits for FNSF magnets are defined as part of the conceptual design studies. The global structural analysis of FNSF magnets based on the radial build was performed to validate feasibility for the plant layout toward horizontal maintenance and global structural integrity of its magnet system.

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Registry

Crossref · 10.1016/j.fusengdes.2017.06.028

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82 of 82 references verified0 citation errors · 0 not checkable

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  • Reasonable radiation operation limits for copper in YBCO HTS magnets are fast neutron fluences up to 2×10^21 n/m2, corresponding to damage levels in the range of mdpa.

    “Reasonable radiation operation limits for copper in Yttrium Barium Copper-Oxide (YBCO) HTS magnets are fast neutron fluences up to 2 × 10 21 n / m 2 , corresponding to damage levels in the range of mdpa [43].”

    From A facility for thermo-mechanical characterization of fusion magnet materials during cryogenic ion irradiation (2025) · cites this paper as [43]

    Table 10 in §8, Radiation Limits (p. 7), lists a fast-neutron-fluence limit of 2×10^21 n/m² for copper in the paper’s discussion of magnet materials. The paper does not state that this fluence corresponds to damage in the mdpa range; that part of the claim is unsupported by our copy. (LLM, conf=0.88)

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Research works printed but not linked: 5

  1. Barth, 2017, On the origins and mechanisms of the irreversible critical current degradation upon mechanical loading: a case study on bronze route niobium-tin wires, Nat. Sci. Rep.
  2. Jong, 2012, ITER magnet structural design criteria part 1: main structural components and welds, ITER IDM UID 2FMHHS
  3. Jong, 2012, ITER magnet structural design criteria part 2: magnet windings (Radial plates and conductors) with high and low voltage insulation and epoxy filler, ITER IDM UID 2ES43V
  4. Jong, 2012, ITER magnet structural design criteria part 3: bolts, keys, supports and special components, ITER IDM UID 2FKTTG
  5. Barzi, 2016, Nb3Sn RRP strand and Rutherford cable development for a 15T dipole demonstrator, IEEE Trans. Appl. Supercond., 26, 4804305, 10.1109/TASC.2016.2535963 · DOI

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Authors
Zhai, Y., Titus, P., Kessel, C., & El-Guebaly, L.
Affiliations
  • Princeton Plasma Physics Laboratory (US)
  • University of Wisconsin–Madison (US)
Corresponding author
Zhai, Yuhu
Venue
Fusion Engineering and Design
Publisher
Elsevier BV
Published
2018-10
Volume
135
Pages
324-336
ISSN
0920-3796 (ISSN-L)
OpenAlex
W2735322322
Cited by
42
References
75
Citations by year
2026: 3 · 2025: 10 · 2024: 3 · 2023: 3 · 2022: 6 · 2021: 7 · 2020: 4 · 2019: 2 · 2018: 2 · 2017: 2
FWCI
1.23
Type
journal article
Language
en
Open access
Locations
  • Fusion Engineering and Design (acceptedVersion)
  • OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) (submittedVersion)
Funders
U.S. Department of Energy (DE-AC02-09CH11466, DE-FG02-98ER54462)
Topics
  • Physical Sciences › Engineering › Biomedical Engineering › Superconducting Materials and Applications
  • Physical Sciences › Physics and Astronomy › Nuclear and High Energy Physics › Magnetic confinement fusion research
  • Physical Sciences › Materials Science › Materials Chemistry › Fusion materials and technologies
Keywords
Fusion Nuclear Science Facility, superconducting magnet design, toroidal field coils, Nb3Sn strands, cable-in-conduit conductors, high-temperature superconductors, low-temperature superconductors, electrical insulation materials, structural analysis, fusion plasma confinement

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