DEALS: a demountable superconducting magnet system for fusion reactors

Powell, J.R.; Hsieh, S.Y.; Danby, G.; Bezler, P.; Gardner, Donald S.; Laverick, C.; Finkelman, M.; Brown, Tom; Bundy, J.; Balderes, Theodore; Zatz, I.; Verzera, R.; Herbermann, R.

doi:10.1016/0011-2275(80)90102-2

Cited by 12 publications

(7 citation statements)

References 2 publications

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“…Although some small-scale laboratory models have been built and tested, no present tokamak incorporates demountable superconducting TF coils. For the present Vulcan study, the most relevant of these conceptual designs is the DEALS magnet system [10], which proposed a demountable TF system using low temperature superconductor (LTS) at 4.2 K. Several generic features of the DEALS system, including resistive joints, are present in the design of the Vulcan TF magnet system. In addition, the Vulcan TF coils incorporate several innovations, including the location of joints at the inner and outer midplane, fabrication of the coils in laminae, and the use of HTS at low temperatures.…”

Section: Demountable Tf Magnetsmentioning

confidence: 99%

“…[10][11][12][13]. Although some small-scale laboratory models have been built and tested, no present tokamak incorporates demountable superconducting TF coils.…”

Section: Demountable Tf Magnetsmentioning

confidence: 99%

“…doi:10.1016/j.fusengdes.2011. 10.002 Table 1 Engineering and plasma parameters for three example operational scenarios for Vulcan. The "A" scenario is full Vulcan performance; the "B" and "C" scenarios are more conservative for the first wall and for the current drive system, respectively.…”

Section: Introductionmentioning

confidence: 99%

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An initial study of demountable high-temperature superconducting toroidal field magnets for the Vulcan tokamak conceptual design

Hartwig

Haakonsen

Mumgaard

et al. 2012

Fusion Engineering and Design

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Section: Demountable Tf Magnetsmentioning

confidence: 99%

“…[10][11][12][13]. Although some small-scale laboratory models have been built and tested, no present tokamak incorporates demountable superconducting TF coils.…”

Section: Demountable Tf Magnetsmentioning

confidence: 99%

See 1 more Smart Citation

An initial study of demountable high-temperature superconducting toroidal field magnets for the Vulcan tokamak conceptual design

Hartwig

Haakonsen

Mumgaard

et al. 2012

Fusion Engineering and Design

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“…This is as opposed to existing machines in which an entire reactor section must be removed (including components internal to the magnets) for the magnets themselves to then be removed. Remountable joints for both low temperature superconductors [32] and high temperature superconductors [5,33,34,35] have been designed, though to-date none have been incorporated into working tokamaks. Indeed there is no published work (at time of writing) demonstrating full-scale remountable joints.…”

Section: Robotics Remountable Magnets and Jointsmentioning

confidence: 99%

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

L.¹,

Surrey²,

Naish³

et al. 2022

Preprint

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All high field superconductors producing magnetic fields above 12 T are brittle. Nevertheless, they will probably be the materials of choice in commercial tokamaks because the fusion power density in a tokamak scales as the fourth power of magnetic field. Here we propose using robust, ductile superconductors during the reactor commissioning phase in order to avoid brittle magnet failure while operational safety margins are being established. Here we use the PROCESS systems code to inform development strategy and to provide detailed capital-cost-minimised tokamak power plant designs. We propose building a 'demonstrator' tokamak with an electric power output of 100 MW e , a plasma fusion gain Q plasma = 17, a net gain Q net = 1.3, a cost of electricity (COE) of $ 1148 (2021 US) per MW h (at 75 % availability) and high temperature superconducting operational TF magnets producing 5.4 T on-axis and 12.5 T peak-field. It uses Nb-Ti training magnets and will cost about $ 9.75 Bn (2021 US). An equivalent 500 MW e plant has a COE of $ 608 per MW suggesting that large tokamaks may eventually dominate the commercial market. We consider a range of designs optimised for capital cost (as the reactors considered are pilot plants) consisting of both 100 MW e and 500 MW e plants with each of two approaches for the magnets: training and upgrading. With training magnets, the plant is cost-optimised for REBCO TF magnets. For a 100 MW e plant, the Nb-Ti training magnets typically produce 70 % peak field on the toroidal field coils compared to REBCO magnets, 65 % peak field on the central solenoid and cost ≈ 10 % of the total machine cost. Training magnets could in principle be reused for each of say 10 subsequent (commercial) machines and hence at 1 % bring only marginal additional cost. With upgrade magnets the plant is more expensive -first it is cost-optimised for Nb-Ti and then upgraded to REBCO coils. The upgrade increases the net electrical output from 100 to 280 MW e with an ≈ 25 % increase in reactor capital cost. We also evaluate likely advances in fusion technology and find that technologies on the horizon will probably not bring further large reductions in capital cost, and that REBCO magnets are generally stress-limited rather than current density limited. We conclude that: the fusion community should develop high B c2 alloys specifically for fusion applications; superconductors should be tested under operational-like radiation at cryogenic temperatures; and that we should proceed now with detailed design and construction of a prototype fusion power plant that integrates and de-risks all the key technologies including high temperature superconducting cables and joints using remountable training magnets, and hence is the last tokamak before commercialisation of fusion energy.

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“…of the HTS coils wound by connecting conductor segments [2,3], and the 'remountable' HTS magnet (here 'remountable' means being able to mount and demount repeatedly) assembled from coil segments with demountable joints [4][5][6]. In the 1980's, a design for a demountable superconducting fusion magnet with low-temperature superconducting materials [7,8] was proposed, however, their low thermal stability and high electric power requirement for running a cryoplant were not acceptable for future developments. HTS materials with high thermal stability can allow magnet operations at a temperature of around 20 K with resistive joints.…”

Section: Introductionmentioning

confidence: 99%

Low-resistance joint development for segment-fabrication of high-temperature superconducting fusion magnets

2021

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Two designs have been proposed for segment-fabrication of the high-temperature superconducting (HTS) helical coils in the FFHR-d1 helical fusion reactor, joint-winding of the HTS coils wound by connecting conductor segments, and the 'remountable' HTS magnet (here 'remountable' means being able to mount and demount repeatedly) assembled from coil segments with demountable joints. A bridge-type mechanical lap joint and mechanical edge joint are planned to be applied to those two designs, respectively. This paper presents the progress in electrical and mechanical performances of the mechanical joints of HTS conductors and methods to evaluate their quality for segment-fabrication of HTS helical coils. R & D of joint performance has progressed during this decade and it shows acceptable performance for the HTS helical coils. The contact-probing current transfer length method and x-ray computer tomography scanning are promising for quality assessment of the joints and HTS tapes.

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DEALS: a demountable superconducting magnet system for fusion reactors

Cited by 12 publications

References 2 publications

An initial study of demountable high-temperature superconducting toroidal field magnets for the Vulcan tokamak conceptual design

An initial study of demountable high-temperature superconducting toroidal field magnets for the Vulcan tokamak conceptual design

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

Low-resistance joint development for segment-fabrication of high-temperature superconducting fusion magnets

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