The IEA Large Coil Task test results in IFSMTF

Clinard, J.A.; Dresner, L.; Fietz, W. A.; Fletcher, W.M.; Haubenreich, P.N.; Lue, J.W.; Luton, J.N.; McManamy, T.J.; Schwenterly, S. W.; Shen, S.; Stamps, R. E.; Wilson, C.T.; Wintenberg, R.E.; Wood, R.; Ulbricht, A.; Friesinger, G.; Wuechner, F.; Okuno, K.; Kato, Takashi; Iida, F.; Takahashi, Yoshikazu; Tsuji, Hiroshi; Hiyama, T.; Zichy, J.; Jakob, B.

doi:10.1109/20.11336

Cited by 7 publications

(1 citation statement)

References 3 publications

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“…D-T) operation has begun, the activation in the reactor vessel would be so high that, given there is no robotic control of magnet replacement, it would probably not be cost-effective to replace a TF coil [11]. Unfortunately all the very high field superconductors that we need in full operation for optimal (profitable) commercial fusion are brittle, and the largest Nb 3 Sn fusion magnets ever produced to-date (by size or weight) were resistive when first turned on [12]. In this paper, we propose using Nb-Ti during the critical commissioning and testing phase because although it has poorer high field performance, it is ductile and so is robust against mechanical or brittle failure.…”

Section: Introductionmentioning

confidence: 99%

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

L.¹,

Surrey²,

Naish³

et al. 2022

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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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Section: Introductionmentioning

confidence: 99%

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

L.¹,

Surrey²,

Naish³

et al. 2022

Preprint

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Conductor Design for The GEM Detector Magnet

et al. 1994

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This report was preparedas an accountof work sponsoredby an agency of the United States Government. Neither the United States Government or =my agency thereof, nor any of their employees, makesany warranty,oxpre, or implied,or mumes any legal liabilityor responsibility for the accuracy, completeness, or usefulnessofany Information, _retus, product,or pro(e. disclosed,or representsthat its use would notInfdnge priwtely owned rights.Referencehereinto any specificcommercial product,process,or service by tradename, treOemark,manufacturer, or otherwiao,doesnot necessarilyco,_stitute or imply its endorsement, recommendation, or favoring by the United Ststes Govemmorttor any agency thereof. The views and opinionsof authors oxpreleed hereindo notnecemdly stateor reflectthole of the United StatesGovernmentor any agencythereof.

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Testing of the Euratom LCT coil in the toroidal arrangement of the International Fusion Superconducting Magnet Test Facility without external pulsed fields (standard-I) and with them (standard II) and an extended single-coil test

et al. 1988

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k w t r r n n d l n m n u v x h . b mIldI0r.d bv I mnlrrm OI lhl us. 775 tanmnt vda mnar( No IK-*co684w21ux) -. h. us. OOrmmntmtmm.-. h. WUbd fm d rm cmabumn. 0. . l m o h m do so. AbstractTesting of the European LCT coil, a forced-flow NbTi coil, with the five other coils in the International Fusion Superconducting Magnet Test Facility (IFSMTF) has been in progress since the beginning of 1986. By the end of July 1987, the Euratom-LCT coil had passed a single-coil test, a test in toroidal configuration with and without poloidal field transients, and an extended single-coil test up to its design limits. In this test, the coil reached, in stable operation, a field of 9 T at 140% of rated current. It reached the short-sample values of the strands used in the cable. The coil was operated up to 8 T with and without poloidal field transients in a toroidal configuration. The mass flow rate was reduced by a factor of 5 compared with the design value without any visible impact on stability. Averaged ac losses (winding, 14 W; case, 7 W) were measured under LCT specified poloidal field pulses, and the findings agreed with those of the short-sample measurements. The mechanical properties behaved as predicted by calculations. No global movement of the winding in the coil case was found, although the coil has already experienced 50% (14 MN) of the maximum out-of-plane force. The operating limits were determined by measuring the current-sharing temperature. It was found that the helium mass flow rate had an impact on the hot-spot temperature of a normal region. All results obtained demonstrate that the applied technology has achieved reliable engineering standards.

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The IEA Large Coil Task test results in IFSMTF

Cited by 7 publications

References 3 publications

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

Training and Upgrading Tokamak Power Plants with Remountable Superconducting Magnets

Conductor Design for The GEM Detector Magnet

Testing of the Euratom LCT coil in the toroidal arrangement of the International Fusion Superconducting Magnet Test Facility without external pulsed fields (standard-I) and with them (standard II) and an extended single-coil test

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