ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets

  title={ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets},
  author={Brandon N. Sorbom and Justin Ball and T. R. Palmer and Franco Julio Mangiarotti and J. M. Sierchio and P. T. Bonoli and C. P. Kasten and D. A. Sutherland and Harold S. Barnard and Christian Bernt Haakonsen and J. Goh and C. Sung and Dennis G. Whyte},
  journal={Fusion Engineering and Design},
The affordable, robust, compact (ARC) reactor is the product of a conceptual design study aimed at reducing the size, cost, and complexity of a combined fusion nuclear science facility (FNSF) and demonstration fusion Pilot power plant. ARC is a ∼200–250 MWe tokamak reactor with a major radius of 3.3 m, a minor radius of 1.1 m, and an on-axis magnetic field of 9.2 T. ARC has rare earth barium copper oxide (REBCO) superconducting toroidal field coils, which have joints to enable disassembly. This… Expand
The engineering design of ARC: A compact, highfield, fusion nuclear science facility and demonstration power plant
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Neutronics Scoping Studies for Experimental Fusion Devices
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Exploration of a Fast Pathway to Nuclear Fusion: Thermal Analysis and Cooling Design Considerations for the ARC Reactor
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Defect Tolerant High-Temperature Superconducting Cable for the Central Solenoid of Compact Fusion Reactor
The future compact fusion reactors, will feature very high, >16 tesla, magnetic fields, which can be only created by magnet coils wound with the second generation (2G) superconducting wire. The 2GExpand


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A potentially attractive next-step towards fusion commercialization is a pilot plant, i.e. a device ultimately capable of small net electricity production in as compact a facility as possible and inExpand
An initial study of demountable high-temperature superconducting toroidal field magnets for the Vulcan tokamak conceptual design
Abstract Recent developments have made it possible to consider high-temperature superconductor (HTS) for the design of tokamak toroidal field (TF) magnet systems, potentially influencing the overallExpand
Vulcan: A steady-state tokamak for reactor-relevant plasma–material interaction science
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Assessing the feasibility of a high-temperature, helium-cooled vacuum vessel and first wall for the Vulcan tokamak conceptual design
Abstract The Vulcan conceptual design (R = 1.2 m, a = 0.3 m, B0 = 7 T), a compact, steady-state tokamak for plasma–material interaction (PMI) science, must incorporate a vacuum vessel capable ofExpand
Demountable Toroidal Field Magnets for Use in a Compact Modular Fusion Reactor
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The ARIES-AT study was initiated to assess the potential of high-performance tokamak plasmas together with advanced technology in a fusion power plant and to identifying physics and technology areasExpand
Design of the TF Coil for a Tokamak Fusion Power Reactor with YBCO Tape Superconductors
  • T. Ando, S. Nishio
  • Materials Science
  • 21st IEEE/NPS Symposium on Fusion Engineering SOFE 05
  • 2005
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Abstract The steady-state current drive system for the Vulcan tokamak concept has been designed, taking into account requirements of high field, small size, and high operational wall temperature (B0Expand