Current-carrying element based on second-generation high-temperature superconductor for the magnet system of a fusion neutron source

Новиков, Михаил С.; Ivanov, D.P.; Novikov, S. I.; Shuvaev, S. A.

doi:10.1134/s1063778815100087

Cited by 6 publications

(7 citation statements)

References 2 publications

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“…An exper imental device for the cables manufacturing was created and successfully tested. This device allows winding of up to 16 tapes in one pass onto a former with length up to 200-300 m. The 2 G HTS helical cables in conduit, consisting of hundreds tapes on flat rounded formers, see figure 2 right, is proposed for the currently projected Fusion Neutrons Source and other toka maks, with a design current 20-35 kA at 10-20 K, and having temperature margin of about 5 K in maximum magn etic fields 12-20 T [26].…”

Section: High Current Hts Cablesmentioning

confidence: 99%

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High temperature superconductors for fusion magnets

Fietz²,

et al. 2018

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The commercially available high temperature superconductors (HTS) tapes and wires (BSSCO and REBCO) are introduced and the past and present projects to build fusion devices using HTS based magnets are reviewed. The main design options for high current, high field conductors are presented with the related R&D and the open issues. Depending on the material, the cable layout and the application specific needs, the challenges for HTS magnet technology are different, ranging from the anisotropic properties of the REBCO tapes, to the large volume heat treatment under high pressure for Bi-2212, to the ability to withstand the large transverse loads, to the optimization of the electrical connections for segmented coil assembly, to the ambitious target of fully demountable TF coils for tokamaks. For the generation of magnetic fields larger than 18–20 T, the HTS represents the enabling technology. The use of the expensive HTS can be better justified for applications, which are out of range for conventional, low temperature superconductors (LTS). Eventually, a roadmap for future R&D is sketched focusing on medium term technology milestones, e.g. addressing the issue of quench protection in HTS large magnets, the industrial manufacture of robust high current HTS cables and the engineering design/demonstration of demountable winding packs.

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Section: High Current Hts Cablesmentioning

confidence: 99%

“…In 2018, many designs of fusion devices worldwide include the use of coils made by HTS high current cables. The individ ual status and achievements are reported for the EUROfusion DEMO in [20,21], for the Chinese CFETR in [22] and for the activities in USA [23,24], Russia [25,26] and Japan for the helical fusion reactor FFHR [27,28].…”

Section: Introductionmentioning

confidence: 99%

High temperature superconductors for fusion magnets

Fietz²,

et al. 2018

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“…The lift factor is defined as the ratio of the critical current at a certain orientation and amplitude of the magnetic field and temperature to the critical current at 77 K with self-field. The experimental lift factors, shown in figure 4, were globally fit to (10) equal to 49. This critical current is about 33% lower than the expected I c value obtained from the sum of the individual tape I c values (162.6 A, with n-index = 32), and it can be explained by the self-field effect on the critical current [21].…”

Section: Experiments #1: Stack Of 20 Tapesmentioning

confidence: 99%

“…With today's performance, it is already feasible to design magnet systems for advanced fusion reactors using this material. In facts, many designs worldwide rely on the use of winding coils made by HTS cables (the EUROfusion DEMO [5,6], the Chinese CFETR [7] the ARC advanced tokamak [8] and the FNSF [9] in the United States, the Fusion Neutron Source [10] in Russia, and the Japanese helical fusion reactor FFHR [11,12]).…”

Section: Introductionmentioning

confidence: 99%

Experimental and numerical studies on current distribution in stacks of HTS tapes for cable-in-conduit-conductors

Marzi¹,

Celentano²,

Augieri³

et al. 2021

Supercond. Sci. Technol.

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Cable-in-conduit conductors comprised of twisted stacks of high-temperature superconducting (HTS) tapes constitute a very promising technology by virtue of their easy manufacturing process, flexibility capabilities, and high current densities. In a cable, the current distribution among tapes is one of the key parameters affecting the cable performances. The distribution of current is affected mainly by the self-field configuration (ultimately related to the cable layout) and the termination resistances. In this paper we present a 2D finite element (FE) model, based on the T-A formulation, which computes the magnetic field and current distribution in stacked tapes. This model has been used to describe the experimental V–I results obtained in cables in which different current distributions among tapes are expected. The first case refers to V–I curves of stacks of HTS tapes inserted into ducts formed in the extruded aluminium cylindrical core for a straight cable. The excellent agreement between the experimental findings and the simulation results can be explained in terms of uniform current distribution within the tapes stack, up to the superconducting to normal transition. The second sample, an Al-slotted core Cable-In-Conduit-Conductor, has been bent down to a radius of 0.15 m, and from the measured V–I characteristic of each individual tape, a different tape degradation depending on the tape position within the stack was recorded. The model is able to reconstruct the V–I of the stacks from the characteristic curves of the individual tapes with a satisfactory agreement. The finite element analysis reveals non-uniform current distribution among the tapes, which could expose the cable to a potentially irreversible damage during operation. The proposed FE model constitutes a useful tool for the analysis and predictions of HTS CIC conductor performances and represents a suitable basis for the implementation of more complex models aimed at the design of specific and large applications of this conductor in the next future.

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“…In addition, REBCO coated conductor cables with current capacity of 100 kA are being built and tested for the magnet system of the force-free helical reactor in Japan [14][15][16]. A helical current-carrying element made of REBCO coated conductors is also under development for the fusion neutron source in Russia [17]. Since a compact fusion reactor project relying entirely on REBCO magnets was launched in the United States in 2020 [18], the design of REBCO cables for large-scale fusion reactors has got into full swing.…”

Section: Introductionmentioning

confidence: 99%

Electromechanical behaviour of REBCO coated conductor toroidal field coils for ultra-high-field magnetic-confinement plasma devices

Große

Song

et al. 2022

J. Phys. D: Appl. Phys.

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The development of rare-earth barium copper oxide (REBCO) coated conductors with an extremely high critical current density under ultra-high fields opens up a high-field path towards large-scale fusion. The latest technology has inspired cable-in-conduit conductors (CICC) such as conductor on round core (CORC) wires, twisted stacked tape conductor (TSTC) cables and Rutherford cables with outstanding current-carrying capacities. In order to realise an inductance balance and decrease magnetic diffusion, these cables have been twisted or folded to a certain extent, thus breaking the mechanical behaviour of the ceramic superconductor and limiting their potential for ultra-high-field applications. One possible solution is to employ a non-twisted cable, which offers maximum protection of its mechanical properties and enables a parallel orientation of the toroidal field vector to the surface of REBCO coated conductors. However, the applied physics community’s attitude towards using non-twisted, parallel REBCO stacked-tape cables is one of scepticism, the main argument being that the nonlinear E-J behaviour associated with screening current in the parallel stack might lead to a field distortion and reduce the performance of superconductivity. Recent analyses have demonstrated that the effect of screening current decreases significantly owing to a wavelike magnetic field distribution along the cable. The authors obtained similar results using H-formulation and T-A formulation based finite element methods and demonstrated that the non-twisted cable may be feasible for DC current transmission toroidal field coils in magnetic-confinement devices. Furthermore, the electromechanical behaviour of toroidal field coils has been evaluated via the Maxwell stress, solved by using an A-V formulation. It was discovered that the stress generated by the toroidal field coils is within the stress tolerance of the REBCO coated conductor, something which is of great significance in promoting the application of REBCO coated conductors for ultra-high-field magnetic-confinement plasma devices.

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Current-carrying element based on second-generation high-temperature superconductor for the magnet system of a fusion neutron source

Cited by 6 publications

References 2 publications

High temperature superconductors for fusion magnets

High temperature superconductors for fusion magnets

Experimental and numerical studies on current distribution in stacks of HTS tapes for cable-in-conduit-conductors

Electromechanical behaviour of REBCO coated conductor toroidal field coils for ultra-high-field magnetic-confinement plasma devices

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