Journal Article10.13182/FST60-648
Design Progress on the High-Temperature Superconducting Coil Option for the Heliotron-Type Fusion Energy Reactor FFHR
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TL;DR: In this paper, the effect of error magnetic field generated by the shielding currents in high-temperature superconductors (HTS) tapes was examined using an FEM analysis for double-pancake windings.
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Abstract: Feasibility studies on applying high-temperature superconductors (HTS) to the heliotron-type fusion energy reactor FFHR are being carried out. Using HTS, we consider that the three-dimensional helical coils with a ~40 m diameter can be constructed without preparing a huge winding machine. A practical method for realizing this concept is proposed. The electromagnetic stress inside the helical coil packs is examined using an FEM analysis for double-pancake windings. The effect of error magnetic field generated by the shielding currents in HTS tapes is also examined.
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Citations
High temperature superconductors for fusion magnets
Pierluigi Bruzzone,Walter H. Fietz,Joseph Minervini,Mikhail Novikov,Nagato Yanagi,Yuhu Zhai,Jinxing Zheng +6 more
Abstract: 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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Helical reactor design FFHR-d1 and c1 for steady-state DEMO
Akio Sagara,Hitoshi Tamura,Teruya Tanaka,Nagato Yanagi,Junichi Miyazawa,Takuya Goto,Ryuichi Sakamoto,Juro Yagi,Tsuguhiro Watanabe,Sadatsugu Takayama +9 more
TL;DR: In this article, a new Flinabe blanket mixed with metal powder was proposed to protect the diverter targets from fast neutrons in the LHD-type helical reactor FFHR-d1.
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HTS CroCo: A Stacked HTS Conductor Optimized for High Currents and Long-Length Production
Michael J. Wolf,Walter H. Fietz,Christoph M. Bayer,Sonja I. Schlachter,Reinhard Heller,Klaus-Peter Weiss +5 more
TL;DR: In this article, a modified type of stacked HTS tape arrangement optimized for high engineering critical current density was developed and tested for high-current cables. But the performance of this tape was not evaluated.
114
Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor
Nagato Yanagi,Satoshi Ito,Y. Terazaki,Y. Seino,Shinji Hamaguchi,Hitoshi Tamura,J. Miyazawa,Toshiyuki Mito,Hidetoshi Hashizume,Akio Sagara +9 more
TL;DR: An innovative winding method is developed by connecting high-temperature superconducting (HTS) conductors to enable efficient construction of a magnet system for the helical fusion reactor FFHR-d1 as discussed by the authors.
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References
Goal and Achievements of Large Helical Device Project
A. Komori,Hiroshi Yamada,Shinsaku Imagawa,Osamu Kaneko,Kazuo Kawahata,K. Mutoh,Nobuyoshi Ohyabu,Y. Takeiri,Katsumi Ida,Toshiyuki Mito,Yoshio Nagayama,Satoru Sakakibara,Ryuichi Sakamoto,Takashi Shimozuma,K.Y. Watanabe,O. Motojima +15 more
TL;DR: The Large Helical Device (LHD) is a heliotron-type device employing large-scale superconducting magnets to enable advanced studies of netcurrent-free plasmas as mentioned in this paper.
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Options for the use of high temperature superconductor in tokamak fusion reactor designs
TL;DR: In this article, the use of high temperature superconductors (HTS) in long term tokamak fusion reactors is analyzed and the consequences of implementing an HTS configuration in a fusion environment are described.
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Optimization activities on design studies of LHD-type reactor FFHR
Akio Sagara,Osamu Mitarai,Teruya Tanaka,Shinsaku Imagawa,Y. Kozaki,Makoto I. Kobayashi,Tomohiro Morisaki,Tsuguhiro Watanabe,Kazuya Takahata,Hitoshi Tamura,Nagato Yanagi,K. Nishimura,Hirotaka Chikaraishi,Shuichi Yamada,Satoshi Fukada,Suguru Masuzaki,A.A. Shishkin,Yuri Igitkhanov,T. Goto,Yuichi Ogawa,Takeo Muroga,Toshiyuki Mito,O. Motojima +22 more
TL;DR: In this paper, three candidates to secure the blanket space are proposed with the aim of reactor size optimization without deteriorating α-heating efficiency and by taking cost analyses into account, and it is demonstrated that the peaking factor of the neutron wall loading is 1.2-1.3 and a blanket covering ratio of over 90% is possible by proposing discrete pumping with a semi-closed shield (DPSS) concept.
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Extended Steady-State and High-Beta Regimes of Net-Current Free Heliotron Plasmas in the Large Helical Device
O. Motojima,H. Yamada,A. Komori,Nobuyoshi Ohyabu,O. Kaneko,Kazuo Kawahata,Toshiyuki Mito,Takashi Mutoh,Katsumi Ida,Shinsaku Imagawa,Y. Nagayama,Takashi Shimozuma,K. Y. Watanabe,Suguru Masuzaki,J. Miyazawa,Tomohiro Morisaki,Satoshi Morita,Satoshi Ohdachi,Noriyasu Ohno,Kenji Saito,Satoru Sakakibara,Y. Takeiri,Naoki Tamura,K. Toi,Masayuki Tokitani,M. "Yokoyama,Mikiro Yoshinuma,K. Ikeda,Akihiko Isayama,Kameo Ishii,S. Kubo,Sadayoshi Murakami,Kazunobu Nagasaki,Tetsuo Seki,Kazuya Takahata,Hidenobu Takenaga +35 more
- 01 Aug 2006
Conceptual design of an indirect-cooled superconducting magnet for the LHD-type fusion reactor FFHR
Kazuya Takahata,Toshiyuki Mito,Hitoshi Tamura,Shinsaku Imagawa,Akio Sagara +4 more
- 01 Oct 2007
TL;DR: In this paper, a conceptual design of the superconductor and coil for the LHD-type helical reactor (FFHR) superconducting magnet is presented, which has a coil major radius of 14m, magnetic energy of 120 GJ and maximum field of 13 T.
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