Overview of ITER magnet system and European contribution

Sborchia, C.; Soto, Emmaris; Batista, R.; Bellesia, B.; Oliva, A. Bonito; Rebollo, E. Boter; Boutboul, T.; Bratu, E.; Caballero, J.; Cornelis, M.; Fanthome, J.; Harrison, R.; Losasso, M.; Portone, A.; Rajainmäki, H.; Readman, P. W.; Valente, P.

doi:10.1109/sofe.2011.6052218

Cited by 13 publications

(17 citation statements)

References 9 publications

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“…However, the length of the individual CICC cables is 17 m for the bottom leg and 7 m for the top leg. Compared with continuous coil winding such as in ITER (where the length of individual cables is 760 m [75]), ARC requires relatively small lengths of continuous REBCO tape. This allows for more economic quality control of the superconductor, since a defect in a REBCO tape spool can be easily removed with minimal loss of material.…”

Section: Superconducting Cables Performancementioning

confidence: 99%

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

Sorbom

Ball

Palmer

et al. 2015

Fusion Engineering and Design

408

375

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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 allows the vacuum vessel to be replaced quickly, mitigating first wall survivability concerns, and permits a single device to test many vacuum vessel designs and divertor materials. The design point has a plasma fusion gain of Q p ≈ 13.6, yet is fully non-inductive, with a modest bootstrap fraction of only ∼63%. Thus ARC offers a high power gain with relatively large external control of the current profile. This highly attractive combination is enabled by the ∼23 T peak field on coil achievable with newly available REBCO superconductor technology. External current drive is provided by two innovative inboard RF launchers using 25 MW of lower hybrid and 13.6 MW of ion cyclotron fast wave power. The resulting efficient current drive provides a robust, steady state core plasma far from disruptive limits. ARC uses an all-liquid blanket, consisting of low pressure, slowly flowing fluorine lithium beryllium (FLiBe) molten salt. The liquid blanket is low-risk technology and provides effective neutron moderation and shielding, excellent heat removal, and a tritium breeding ratio ≥ 1.1. The large temperature range over which FLiBe is liquid permits an output blanket temperature of 900 K, single phase fluid cooling, and a high efficiency helium Brayton cycle, which allows for net electricity generation when operating ARC as a Pilot power plant.

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Section: Superconducting Cables Performancementioning

confidence: 99%

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

Sorbom

Ball

Palmer

et al. 2015

Fusion Engineering and Design

408

375

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“…To ensure uniform production quality, reference laboratories have measured the properties of the superconducting strands in high fields [1]: 12 T for Nb3Sn and 6.4 T for Nb-Ti at 4.22 K [2]. In standard critical current (IC) measurements at liquid helium temperatures, samples are usually measured on a Ti-6Al-4V wt % (Ti-64) ITER barrel [3].…”

Section: Introductionmentioning

confidence: 99%

Superconducting Properties of Titanium Alloys (Ti-64 and Ti-6242) for Critical Current Barrels

Ridgeon

Raine

Halliday

et al. 2017

IEEE Trans. Appl. Supercond.

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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%

“…It has been optimised for maximum critical current density between ≈ 4 T and 6 T for MRI and accelerator magnet applications [107]. Its relatively low upper critical field (B c2 (4.2 K) ≈ 10 T [108]) means that it has only been used for the poloidal field coils in next generation fusion reactors such as ITER [109] and EU-DEMO [3] (though it is being used for the TF coils in JT60-SA [110]). [111] which has long made it the material of choice for applications when > 10 T fields are required.…”

Section: High Field Superconductorsmentioning

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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Overview of ITER magnet system and European contribution

Cited by 13 publications

References 9 publications

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

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

Superconducting Properties of Titanium Alloys (Ti-64 and Ti-6242) for Critical Current Barrels

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

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