Design of the High-&amp;lt;tex&amp;gt;$rm T_rm c$&amp;lt;/tex&amp;gt;Superconducting TF Coil for the Tight Aspect Ratio Tokamak Power Reactor (VECTOR)

Ando, T.; Nishio, S.; Yoshimura, Hideto

doi:10.1109/tasc.2004.830659

Cited by 10 publications

(3 citation statements)

References 7 publications

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“…The SS conduit adopted for ITER will have difficulty by a large reduction of J c due to the large strain due to the difference in thermal expansion coefficient between SS and Nb 3 Sn. High T c superconductors are attractive technology for the magnetic confinement fusion providing Conductor type compact reactor configuration such as VECTOR [42] where the high T c conductor designs are successfully developed [43,44]. As long as Nb 3 Sn design is possible, it is more reliable and economical at present to use Nb 3 Sn design.…”

Section: Conductor Design Of Tf Coilsmentioning

confidence: 99%

L-mode-edge negative triangularity tokamak reactor

et al. 2019

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The negative triangularity tokamak (NTT) is a unique reactor concept based on "powerhandling-first" philosophy with the heat exhaust problem as the leading concern. The present paper exposes a reactor concept using L-mode edge based on negative triangularity tokamak (NTT) configuration, providing merits of no (or very weak) ELMs, larger particle flux and large major radius for power handling. It is shown that a reasonably compact (R p from 9m to 7m) NTT reactor is possible by achieving higher confinement improvement (H H =1.5) and/or by utilizing reasonably higher magnetic field (B max =15.5T). Current physics basis and critical issues on its scientific and technical feasibility are discussed. 1. PHYSICS BACKGROUND OF NTT REACTOR

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Section: Conductor Design Of Tf Coilsmentioning

confidence: 99%

L-mode-edge negative triangularity tokamak reactor

et al. 2019

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“…However, this path was later terminated, due to the high silver content of this type of superconductor, which could be highly activated by neutron irradiation. The pioneering design of the HTS tokamak magnets using YBCO tapes was also initiated around the same time [14,15].…”

Section: High-temperature Superconducting Magnet Option With Joint-wi...mentioning

confidence: 99%

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

et al. 2015

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“…Considering these advantages, the conceptual design studies on the use of HTS materials in tokamak reactors were carried out for ARIES-AT [10] and VECTOR [11] more than 10 years ago. Along with the design of VEC-TOR, a 10-kA-class CIC conductor using round Bi-2212 HTS strands was successfully tested [12].…”

Section: Introductionmentioning

confidence: 99%

Feasibility of HTS Magnet Option for Fusion Reactors

Yanagi

Terazaki

Natsume

et al. 2014

Plasma and Fusion Research

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Conceptual design studies are being carried out on the application of high-temperature superconducting (HTS) conductors and coils to the magnet systems of fusion reactors. A 100-kA-class HTS conductor is required to be applied at high magnetic fields of > 12 T. A simple stack of YBCO tapes embedded in copper and stainless-steel jackets is found to be a practical approach to producing large-scale conductors that exhibit high cryogenic stability and mechanical rigidity. The feasibility of the segmented fabrication method for large complex HTS coils, such as the helical coils in the LHD-type helical fusion reactor FFHR-d1, is being investigated by developing mechanical bridge-type lap joint technology of HTS conductors.

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Design of the High-<tex>$rm T_rm c$</tex>Superconducting TF Coil for the Tight Aspect Ratio Tokamak Power Reactor (VECTOR)

Cited by 10 publications

References 7 publications

L-mode-edge negative triangularity tokamak reactor

L-mode-edge negative triangularity tokamak reactor

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

Feasibility of HTS Magnet Option for Fusion Reactors

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