Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors

Liu, Xiaogang; Wu, Fan; Wang, Zhaoliang; Li, Guoqiang; Li, Hang; Li, Junjun; Ren, Yong; Wang, Yu; Gao, Xiang

doi:10.1088/1741-4326/ab742d

Cited by 26 publications

(7 citation statements)

References 29 publications

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“…Among others, the CFETR TF prototype coil, which is a full-scale prototype coil for developing the key technologies and processes, such as highperformance superconducting strand and cable-in-conduit conductor (CICC), coil winding and coil case manufacture, e.g. [3,4].…”

Section: Introductionmentioning

confidence: 99%

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Dai

Wang

et al. 2021

Nucl. Fusion

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The Comprehensive Research Facility for Fusion Technology (CRAFT) project has been launched in 2019, for developing the essential engineering technologies for Chinese Fusion Engineering Testing Reactor (CFETR). Within this project, a full-size toroidal field (TF) coil will be built as the prototype coil for CFETR. Based on design of CFETR magnet system, the TF coil will operate at 95.6 kA in a peak field of 14.5 T. The high-J c Nb3Sn strand is taken into consideration due to the critical current density of ITER-grade Nb3Sn is too low at 14.5 T. Considering that it will be the first time to apply the high-J c Nb3Sn strand in the large-scale cable-in-conduit conductor (CICC) for fusion magnet, a conductor sample made of high-J c Nb3Sn strand with short twist pitch (STP) cable pattern was manufactured in ASIPP and tested in SULTAN facility, to investigate the feasibility. The test campaign focuses on the impact of cyclic electromagnetic (EM) loading and warm-up cool-down (WUCD) to the performance of the conductor, the strain distribution of the conductor before and after EM cycles was measured by inductive method to make a deeper insight of the conductor performance evolution. AC losses tests have also been carried out, providing relevant information for further coil design.

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Section: Introductionmentioning

confidence: 99%

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Dai

Wang

et al. 2021

Nucl. Fusion

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“…It should include all the key technologies and identify whether fission power plants can be replaced on a commercial footing by fusion power plants that produce no long-term high-level waste, reduce proliferation of nuclear weapons in a increasingly carbon-free world, and provide long-term energy security for base load electricity production. [156], ARC [5], CFETR [193,206], ITER [1,109], SPARC [2,207], JET [166,208,209], JT60-SA [103,110], KSTAR [210,211,212], EAST [213,214,215], WEST [216,217], MAST-U [153,218] and SST-1 [219,220] [108,111,130,134], and B c2 (T ) = B c2 (0)(1 − t) s for REBCO [120].…”

Section: Discussionmentioning

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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“…The TF coil is one of the most important superconducting coils, it defines the shape of the tokamak, the major radius and the toroidal field [2]. And the encapsulated TF case consists of four segments, U shaped enclosures (AU/BU) and its cover plates (AP/BP), which encasing TF winding pack.…”

Section: Heat Load Analysis Of Cfetr Tf Magnet Test Facilitymentioning

confidence: 99%

Preliminary analysis and design of 4kW@4.5K helium refrigerator for CFETR toroidal field magnet test facility

Zhang

Zhou

et al. 2022

IOP Conf. Ser.: Mater. Sci. Eng.

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China Fusion Engineering Test Reactor (CFETR) is the next magnetic confinement fusion device to demonstrate fusion energy. To test the cryogenic performance of CFETR Toroidal Field (TF) superconducting magnet, a large-scale helium cryogenic system was under construction to provide Supercritical Helium (SHe), supported by Comprehensive Research Facility for Fusion Technology (CRAFT). In this paper, heat loads of TF magnet and the dedicated distribution system were analysed to define the scale. Process flow of the helium refrigerator has been designed considering the various operation phases. Preliminary thermodynamic cycle of the helium refrigerator have been calculated with the capacity of 4kW@4.5K+20g/s@50K. This 4kW@4.5K helium refrigerator was not only a test facility for CFETR superconducting magnets, but also a prototype of CFETR helium refrigerator.

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Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors

Cited by 26 publications

References 29 publications

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

Preliminary analysis and design of 4kW@4.5K helium refrigerator for CFETR toroidal field magnet test facility

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Progress in the conceptual design of the CFETR toroidal field coil with rectangular conductors

Cited by 26 publications

References 29 publications

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J c Nb3Sn strand for fusion reactor

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J c Nb3Sn strand for fusion reactor

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

Preliminary analysis and design of 4kW@4.5K helium refrigerator for CFETR toroidal field magnet test facility

Contact Info

Product

Resources

About

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor

Performance test and analysis of the first large-scale cable-in-conduit conductor with high J _c Nb₃Sn strand for fusion reactor