Feasibility of HTS Magnet Option for Fusion Reactors

Yanagi, N.; Terazaki, Y.; Natsume, Kyohei; Tamura, H.; Hamaguchi, S.; Mito, T.; Hashizume, Hidetoshi; Morikawa, Junji; Ogawa, Yuichi; Iwakuma, Masataka; Sagara, A.

doi:10.1585/pfr.9.1405013

Cited by 10 publications

(6 citation statements)

References 32 publications

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“…For the superconducting magnet system of FFHR-d1, the high-temperature superconductor (HTS) using the Rare-Earth Barium Copper Oxide (REBCO) coated conductor tapes is considered [25][26][27][28] as an alternative option to the original cable-in-conduit conductor using low-temperature superconducting Nb3Sn strands [29,30], which is an extension of the ITER technology. In the present design of the helical coils of FFHR-d1, the number of winding turns is 390 and the conductor current is 94 kA at the maximum magnetic field of 11.8 T [28].…”

Section: Joint-winding Of the Ffhr-d1 Helical Coils With Hts Conductorsmentioning

confidence: 99%

Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1

et al. 2018

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The LHD-type helical fusion reactor FFHR has been studied to realize steady-state fusion power generation without a need for current drive and free from disruption. The conceptual design studies of FFHR are steadfastly progressing based on the presently ongoing experiments in the Large Helical Device (LHD). In order to enhance the attractive features of the base option of FFHR-d1A, which is similar to LHD, configuration optimization is being considered for FFHR-d1C. Slight modification of the helical coil trajectory gives an improved condition both for the plasma confinement and the MHD stability. In order to overcome the difficulty for construction and maintenance associated with the three-dimensional structure, innovative ideas are being explored for the superconducting magnet, divertor, and blanket. For the superconducting helical coils, the joint-winding method confirms a fast manufacturing process. The helical divertor is reexamined and practical feasibility is discussed. The maintenance method of the helical divertor and the helically-segmented breeder blanket is a serious issue and a plausible solution is proposed.

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Section: Joint-winding Of the Ffhr-d1 Helical Coils With Hts Conductorsmentioning

confidence: 99%

Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1

et al. 2018

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“…Several approaches have been developed to combine REBCO coated conductors into the high current cable configuration required for low-inductance, high-field magnets. These configurations include: Roebel bar [6], twisted stack-tape cable [7], conductor-on-round-core (CORC ® ) cables [8] and the aligned, stacked tape cables under development at NIFS [9].…”

Section: Introductionmentioning

confidence: 99%

Behavior of a high-temperature superconducting conductor on a round core cable at current ramp rates as high as 67.8 kA s⁻¹in background fields of up to 19 T

Michael

Bromberg

Laan

et al. 2016

Supercond. Sci. Technol.

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High temperature superconducting (HTS) conductor-on-round-core (CORC ® ) cables have been developed for use in power transmission systems and large high-field magnets. The use of highcurrent conductors for large-scale magnets reduces system inductance and limits the peak voltage needed for ramped field operation. A CORC ® cable contains a large number of RE-Ba 2 Cu 3 O 7−δ (RE=rare earth) (REBCO) coated conductors, helically wound in multiple layers on a thin, round former. Large-scale applications, such as fusion and accelerator magnets, require current ramp rates of several kilo-Amperes per second during pulsed operation. This paper presents results that demonstrate the electromagnetic stability of a CORC ® cable during transient conditions. Measurements were performed at 4.2 K using a 1.55 m long CORC ® cable in background fields of up to 19 T. Repeated current pulses in a background field of 19 T at current ramp rates of up to 67.8 kA s −1 to approximately 90% of the cable's quench current at that field, did not show any sign of degradation in cable performance due to excessive ac loss or electromagnetic instability. The very high current ramp rates applied during these tests were used to compensate, to the extent possible, the limited cable length accommodated by the test facility, assuming that the measured results could be extrapolated to longer length cables operated at proportionally lower current ramp rates. No shift of the superconducting transition to lower current was measured when the current ramp rate was increased from 25 A s −1 to 67.8 kA s −1 . These results demonstrate the viability of CORC ® cables for use in low-inductance magnets that operate at moderate to high current ramp rates.

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“…Highly thermally stable and low cryogenic materials are favorites for such reactors [16]. HTSC and especially REBCO, where RE indicates the rare earth elements and BCO is barium copper oxides tapes have prominent aspects like greater cryogenic constancy alike the thermal ability of distinctive metals [17],…”

Section: Htsc For Fusion Reactorsmentioning

confidence: 99%

High Temperature Superconductors: Materials and Applications

Hasan

2022

Superconductors

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A ceramic high temperature superconductor called cuprate was discovered in 1986 by Bednorz and Muller at 135 K critical temperature (Tc). Ladik and Bierman demonstrated the idea of high temperature superconductivity (HTSC) by essential excitation of electrons in one chain of double standard DNA. The cuprates are consisted of stiff, fragile, and hard properties which are considered as the negative impact of cuprates superconductors. With the passage of time such drawback were removed and the cuprate superconductors were made capable for various applications. The breakthrough came in the history of superconductors when the iron based HTSC were discovered in 2006. High temperature H2S superconductors are designed at high pressure and Tc greater than 200 K in 2015. From the time of discovery of HTSC, superconductivity is used in different types of fields such as medical, electrical, magnetic, optics, recording media, microwave and communication devices.

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Feasibility of HTS Magnet Option for Fusion Reactors

Cited by 10 publications

References 32 publications

Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1

Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1

Behavior of a high-temperature superconducting conductor on a round core cable at current ramp rates as high as 67.8 kA s⁻¹in background fields of up to 19 T

High Temperature Superconductors: Materials and Applications

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Feasibility of HTS Magnet Option for Fusion Reactors

Cited by 10 publications

References 32 publications

Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1

Progress in the Conceptual Design of the Helical Fusion Reactor FFHR-d1

Behavior of a high-temperature superconducting conductor on a round core cable at current ramp rates as high as 67.8 kA s−1in background fields of up to 19 T

High Temperature Superconductors: Materials and Applications

Contact Info

Product

Resources

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Behavior of a high-temperature superconducting conductor on a round core cable at current ramp rates as high as 67.8 kA s⁻¹in background fields of up to 19 T