Zobrazeno 1 - 10 of 105 pro vyhledávání: '"Shinji HAMAGUCHI"'
1
Improvement of Ic degradation of HTS Conductor (FAIR Conductor) and FAIR Coil Structure for Fusion Device
Autor: Akifumi Kawagoe, Kazuya Takahata, Suguru Takada, Nagato Yanagi, Ryozo Kawanami, Noriko Chikumoto, Shinji Hamaguchi, Maki Otsuji, Toshiyuki Mito, Akifumi Iwamoto, Naoki Hirano, Yuta Onodera, T. Baba
Publikováno v: T. Mito et al., "Improvement of Ic degradation of HTS Conductor (FAIR Conductor) and FAIR Coil Structure for Fusion Device," in IEEE Transactions on Applied Superconductivity, vol. 31, no. 5, pp. 1-5, Aug. 2021, Art no. 4202505, doi: 10.1109/TASC.2021.3069923.
As a high-temperature superconducting (HTS) conductor with a large current capacity applicable to a nuclear fusion experimental device, REBCO (REBa 2 CuO y ) tapes and high-purity aluminum sheets are alternately laminated, placed in a groove of an al
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d6a46cc36ce913b9562e9253796725aa
https://doi.org/10.1109/tasc.2021.3069923
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2
Results of All ITER TF Full-Size Joint Sample Tests in Japan
Autor: Kazumi Yoshizawa, Mio Nakamoto, Minoru Yamane, Norikiyo Koizumi, Hirotaka Chikaraishi, Shinsaku Imagawa, Shinji Hamaguchi, Tetsuhiro Obana, Hideki Kajitani, Kunihiro Matsui, Suguru Takada, Yasuhiro Uno, Masataka Nakahira
Publikováno v: H. Kajitani et al., "Results of All ITER TF Full-Size Joint Sample Tests in Japan," in IEEE Transactions on Applied Superconductivity, vol. 31, no. 5, pp. 1-5, Aug. 2021, Art no. 4201905, doi: 10.1109/TASC.2021.3064004.
Nine toroidal field (TF) coils have been developed in Japan for the international thermonuclear experimental reactor (ITER). The joint resistance of TF coil should satisfy the requirement of smaller than 3 nano-ohm at 2 T of external magnetic field a
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::07a8506d17633409933529da3e6e4f40
https://doi.org/10.1109/tasc.2021.3064004
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4
Progress of HTS STARS Conductor Development for the Next-Generation Helical Fusion Experimental Device
Autor: Nagato YANAGI, Yoshiro TERAZAKI, Yoshiro NARUSHIMA, Yuta ONODERA, Naoki HIRANO, Shinji HAMAGUCHI, Hirotaka CHIKARAISHI, Suguru TAKADA, Satoshi ITO, Kazuya TAKAHATA
Publikováno v: Plasma and Fusion Research. 17:2405076-2405076
A High-Temperature Superconducting (HTS) magnet is being considered to for use in the next-generation helical experimental devices. Three types of large-current HTS conductors are being developed, and one of them is the STARS (Stacked Tapes Assembled
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5c95abc9c696a7eeef978710448ffe3b
https://doi.org/10.1585/pfr.17.2405076
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5
Design, Fabrication and Soundness Test of A Bi2223 Magnet Designed for Cooling by Liquid Hydrogen
Autor: Shinsaku Imagawa, Akifumi Iwamoto, Shinji Hamaguchi, Yasuyuki Shirai, Rikako Kawasaki, Hikaru Ohya, Fumiya Matsumoto, Masahiro Shiotsu, Makoto Tsuda, Yoh Nagasaki, Tsuyoshi Yagai, Hiroaki Kobayashi
Publikováno v: S. Imagawa et al., "Design, Fabrication and Soundness Test of A Bi2223 Magnet Designed for Cooling by Liquid Hydrogen," in IEEE Transactions on Applied Superconductivity, vol. 32, no. 6, pp. 1-5, Sept. 2022, Art no. 4604605, doi: 10.1109/TASC.2022.3172271.
The critical heat flux in liquid hydrogen is ten times higher than that in liquid helium and is approximately half of that in liquid nitrogen. Since the resistivity of pure metal such as copper or silver at 20 K is less than one-hundredth of that at
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::61520196bc56504293a5aac40f900534
http://hdl.handle.net/10655/00013466
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6
Simulation of Decay of Shielding Currents in ITER-TF Joint Samples
Autor: Shinsaku IMAGAWA, Hideki KAJITANI, Tetsuhiro OBANA, Suguru TAKADA, Shinji HAMAGUCHI, Hirotaka CHIKARAISHI, Yuta ONODERA, Kazuya TAKAHATA, Kunihiro MATSUI, Norikiyo KOIZUMI
Publikováno v: Plasma and Fusion Research. 17:2405021-2405021
As a qualification test of ITER-TF coils, each joint sample was tested prior to manufacture of each TF coil. Eleven joint samples were tested by a conductor test facility with a 9 T split coil. The joint sample comprised two short TF conductors that
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4af8920fd43679dfea256dfd1ae782a2
https://doi.org/10.1585/pfr.17.2405021
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7
Test of 10 kA-Class HTS WISE Conductor in High Magnetic Field Facility
Autor: Yoshiro NARUSHIMA, Yoshiro TERAZAKI, Yuta ONODERA, Nagato YANAGI, Naoki HIRANO, Shinji HAMAGUCHI, Hirotaka CHIKARAISHI, Tomosumi BABA, Junichi MIYAZAWA
Publikováno v: Plasma and Fusion Research. 17(Special Issue 1):2405006
High-temperature superconducting (HTS) conductor is a feasible candidate to make magnets for the next generation fusion devices because of its higher temperature margins and higher critical current in a high magnetic field in comparison to low-temper
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f5decc2427faf47098ac635a3d92ef1f
http://hdl.handle.net/10655/00013086
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8
Investigation of long time constants of magnetic fields generated by the JT-60SA CS1 module
Autor: Haruyuki Murakami, Kazuya Takahata, Suguru Takada, Hirotaka Chikaraishi, Shinji Hamaguchi, Tetsuhiro Obana, Kyohei Natsume, Kaname Kizu, Shinsaku Imagawa, Toshiyuki Mito, Akifumi Iwamoto
Publikováno v: Tetsuhiro Obana, Kazuya Takahata, Shinji Hamaguchi, Hirotaka Chikaraishi, Suguru Takada, Akifumi Iwamoto, Shinsaku Imagawa, Toshiyuki Mito, Haruyuki Murakami, Kyohei Natsume, Kaname Kizu, Investigation of long time constants of magnetic fields generated by the JT-60SA CS1 module, Fusion Engineering and Design, Volume 137, 2018, Pages 274-282, ISSN 0920-3796, https://doi.org/10.1016/j.fusengdes.2018.10.005.
In a cold test of the JT-60SA CS1 module, which is composed of six octa-pancake coils and one quad-pancake coil wound with Nb3Sn CIC conductors, the measurement of self-magnetic fields generated by the CS1 module was conducted. As a result, the decay
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::83fe4fb835d8826a444fb8df0b405276
http://hdl.handle.net/10655/00012958
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9
Reexamination of Refrigeration Power of the LHD Cryogenic System After Fire and Restart of Operation
Autor: Katsuhiro Nakamura, Akifumi Iwamoto, Nagato Yanagi, Kazuya Takahata, Shigeharu Kuwahara, Toshiya Nakashima, Koji Obara, Toshiyuki Mito, S. Moriuchi, Shinji Hamaguchi, Shinsaku Imagawa, K. Oba, Takuya Kumaki, Minoru Nobutoki, S. Takami, Hiroki Noguchi
Publikováno v: T. Mito et al., "Reexamination of Refrigeration Power of the LHD Cryogenic System After Fire and Restart of Operation," in IEEE Transactions on Applied Superconductivity, vol. 28, no. 4, pp. 1-4, June 2018, Art no. 4206004, doi: 10.1109/TASC.2018.2810517.
The Large Helical Device (LHD), built in the 1990s, is a heliotron-type fusion plasma experimental device with the world's first fully superconducting magnetic confinement system. The LHD cryogenic system operated stably for 18 years from 1998 to 201
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2df7ea51cda6a666f0642219c35657ee
https://doi.org/10.1109/tasc.2018.2810517
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10
Test of ITER-TF Joint Samples With NIFS Test Facilities
Autor: Imagawa, Shinsaku, IEEE, Member, KAJITANI, Hideki, OBANA, Tetsuhiro, Takada, Suguru, Shinji, Hamaguchi, Chikaraishi, Hirotaka, Takahata, Kazuya, Matsui, Kunihiro, Hemmi, Tsutomu, Koizumi, Norikiyo
Publikováno v: S. Imagawa et al., "Test of ITER-TF Joint Samples With NIFS Test Facilities," in IEEE Transactions on Applied Superconductivity, vol. 28, no. 3, pp. 1-5, April 2018, Art no. 4200405, doi: 10.1109/TASC.2017.2774368.
Qualification tests of the ITER toroidal field (TF) conductor joints have been carried out by testing joint samples with test facilities in the National Institute for Fusion Science, NINS, Toki, Japan. The joint sample consists of two short TF conduc
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5093fa91e44de910a8c103af6a0a5766
https://doi.org/10.1109/tasc.2017.2774368
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