Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor

Yanagi, N.; Ito, Satoshi; Terazaki, Y.; Seino, Y.; Hamaguchi, S.; Tamura, H.; Miyazawa, J.; Mito, T.; Hashizume, Hidetoshi; Sagara, A.

doi:10.1088/0029-5515/55/5/053021

Cited by 64 publications

(67 citation statements)

References 27 publications

(26 reference statements)

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“…In the present design of the helical coils of FFHR-d1, the number of winding turns is set at 390 and the conductor current of 94 kA produces the toroidal magnetic field of 4.7 T [3]. A fairly large current density of ~25 A/mm 2 is required in the winding area, which exceeds that of the ITER toroidal field (TF) coils of 20 A/mm 2 .…”

Section: Concept Of Hts Option Of Ffhr-d1 Helical Coils With 100 Ka Smentioning

confidence: 99%

“…An advanced option is to use ceramics, which ensures higher thermal contact and higher robustness against neutron irradiation, but requires sufficient technical development. Using the HTS conductor, an innovative winding method is proposed for the helical coils, which is to connect prefabricated conductors onsite [3]. This is referred to "joint-winding".…”

Section: Concept Of Hts Option Of Ffhr-d1 Helical Coils With 100 Ka Smentioning

confidence: 99%

“…We select the high-temperature superconductor (HTS) in the "challenging" option of the FFHR-d1 design [3]. The second generation HTS, the Rare-Earth Barium Copper Oxide (REBCO, represented typically by YBCO and GdBCO) coated conductor tape, is a plausible candidate for this option.…”

Section: Introductionmentioning

confidence: 99%

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Magnet design with 100-kA HTS STARS conductors for the helical fusion reactor

et al. 2016

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Section: Concept Of Hts Option Of Ffhr-d1 Helical Coils With 100 Ka Smentioning

confidence: 99%

Section: Concept Of Hts Option Of Ffhr-d1 Helical Coils With 100 Ka Smentioning

confidence: 99%

See 1 more Smart Citation

Magnet design with 100-kA HTS STARS conductors for the helical fusion reactor

et al. 2016

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“…Cabling methods for the HTS tapes such as Roebel Assembled Coated Conductor (RACC), Conductor-On-Round Core (CORC), Twisted StackedTape Cable (TSTC) and a few other alternates have been proposed [1] - [8].…”

Section: Introductionmentioning

confidence: 99%

Present Status and Recent Developments of the Twisted Stacked-Tape Cable Conductor

Takayasu

Chiesa

Allen

et al. 2016

IEEE Trans. Appl. Supercond.

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High magnetic field performance of a 40-tape Twisted Stacked-Tape Cable (TSTC) conductor made of 4 mm width, 0.1 mm thick REBCO tapes was successfully tested. The critical current was 6.0 kA with the n-value of 35 at 4.2 K with a background field of 17 T. No-cyclic load effect was observed between 10 T and 17 T with the maximum Lorentz load of 102 kN/m. Various issues such as sample length, non-uniformity of termination resistances, soldered joint of a coated tape cable with regards to a TSTC conductor are discussed. Large-scale conductor designs of various scalable TSTC conductors are discussed taking into account current densities and stabilizers.

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“…For example, the helical fusion reactor might be efficiently constructed using a high temperature superconductor (HTS) with jointwinding. A prototype HTS with a bridge-type mechanical lap joint successfully achieved 100 kA at 20 K and a low-resistance (1.8 nΩ) at 4 K [10,11]. A detailed welding method for the joint section is also being investigated.…”

Section: Challenging Optionsmentioning

confidence: 99%

Design Status of the Structural Components of the Helical Fusion Reactor FFHR-d1

Tamura

Tanaka

Goto

et al. 2016

Plasma and Fusion Research

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FFHR-d1 is a conceptual design of the Large Helical Device-type fusion reactor. Several design optimizations for FFHR-d1 have been conducted under a multipath strategy. The structural design began from a radial build design of the components using a system code analysis and considering a shielding/breeding blanket design. The support structure must be sufficiently rigid to hold a constant geometric position of the radial build components. Additionally, large apertures are required for the maintenance work of in-vessel components. The shape of the support structure was carefully chosen and the analytically determined stress level was within the permissible limit. Thus, the basic design of the structural components of FFHR-d1 was established. To accelerate the design activity and achieve a consistent helical reactor system, the high-temperature superconducting joint-winding, liquid metal divertor, a supplemental helical coil addition, a novel divertor structure, and other challenging options are investigated alongside the basic design. This paper describes the structural design status of FFHR-d1 by focusing on the latest radial build design, construction scheme, and effectiveness of the novel divertor structure.

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Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor

Abstract:  HTS prototype conductor sample achieved 100 kA for 1 hour  Mechanical lap-joint confirms low joint resistance (2 nW)  "Joint-winding" of helical coils technically feasible

Cited by 64 publications

References 27 publications

Magnet design with 100-kA HTS STARS conductors for the helical fusion reactor

Magnet design with 100-kA HTS STARS conductors for the helical fusion reactor

Present Status and Recent Developments of the Twisted Stacked-Tape Cable Conductor

Design Status of the Structural Components of the Helical Fusion Reactor FFHR-d1

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