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pro vyhledávání: '"K. Tomabechi"'
Akademický článek
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Autor:
Hiroyuki Furukawa, Takayoshi Norimatsu, K. Tomabechi, J. Kawanaka, K. Mima, Yasuji Kozaki, M. Miyanaga, Hiroshi Azechi
Publikováno v:
Fusion Science and Technology. 52:893-900
Recent progress on fast ignition (FI) and cooled Yb:YAG ceramic laser enable us to design an IFE power plant with a 1MJ-class, compact laser whose output energy is 1/4 of previous central ignition scheme. Basing on the FI scheme, we conceptually desi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0c3d40e66b9545d234f0d5d838abbdab
https://doi.org/10.13182/fst52-893
https://doi.org/10.13182/fst52-893
Autor:
K. Tomabechi, Y. Kozaki, T. Norimatsu, Members of Reactor Design Committee Members of Reactor Design Committee
Publikováno v:
Journal de Physique IV (Proceedings). 133:791-795
A conceptual design of the laser fusion reactor KOYO-F based on the fast ignition scheme is reported including the target design, the laser system and the design for chamber. A Yb-YAG ceramic laser operated at 200K is the primary candidate for the co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f305026c4899a26b1cdbebdad295c022
https://doi.org/10.1051/jp4:2006133160
https://doi.org/10.1051/jp4:2006133160
Publikováno v:
Nuclear Fusion. 44:106-116
This study reveals for the first time the plasma performance required for a tokamak reactor to generate net electric power under foreseeable engineering conditions. It was found that the reference plasma performance of the ITER inductive operation mo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::53ebe9b04d28c3b0ff4e035b3998dfa1
https://doi.org/10.1088/0029-5515/44/1/013
https://doi.org/10.1088/0029-5515/44/1/013
Publikováno v:
Fusion Engineering and Design. :461-466
A maintenance approach of the Compact Reversed Shear Tokamak (CREST) for high availability is proposed. Full sector removal through horizontal ports for easy maintenance is adopted in order to increase availability. Cask type sector removal machines
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d54f86e1b292999ce5c9628095fbf85a
https://doi.org/10.1016/s0920-3796(00)00265-9
https://doi.org/10.1016/s0920-3796(00)00265-9
Publikováno v:
Fusion Engineering and Design. :1025-1032
Feasibility of commercial tokamak reactors is discussed. The range of cost of electricity (COE) by competitors of fusion is estimated and the target range of COE for the fusion reactors is proposed. It is shown that the high β advanced plasma mode w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f4c27749a9d8376003c600d52f9a4c38
https://doi.org/10.1016/s0920-3796(00)00188-5
https://doi.org/10.1016/s0920-3796(00)00188-5
Autor:
Y. Asaoka, Akiyoshi Hatayama, Tomoaki Yoshida, Nobuyuki Inoue, Sei Ichiro Yamazaki, Naoto Sekimura, Kunihiko Okano, Seiji Mori, Yuzo Fukai, Akira Kohyama, Yuichi Ogawa, K. Tomabechi
Publikováno v:
Fusion Engineering and Design. 48:397-405
Conceptual design of a tritium breeding blanket for CREST-1 was conducted. CREST-1 (Compact REversed Shear Tokamak), a conceptual design of water-cooled commercial reactor based on a reversed shear high beta equilibrium, has been proposed as a possib
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a5dd9e87f54005f7491e928d583fe3d2
https://doi.org/10.1016/s0920-3796(00)00149-6
https://doi.org/10.1016/s0920-3796(00)00149-6
Autor:
K. Shinya, Tomoaki Yoshida, T. Ishikawa, Nobuyuki Inoue, J. Adachi, Yuzo Fukai, K. Tomabechi, Akiyoshi Hatayama, Y. Murakami, T. Yamamoto, Akira Kohyama, Y. Asaoka, I. Senda, Naoto Sekimura, Ryoji Hiwatari, M. Takemoto, Seiji Mori, Seiichiro Yamazaki, Kunihiko Okano, Masahiro Furuya, Yuichi Ogawa
Publikováno v:
Nuclear Fusion. 40:635-646
The compact reversed shear tokamak CREST is a cost competitive reactor concept based on a reversed shear high β plasma and water cooled ferritic steel components. The moderate aspect ratio A = 3.4 and the elongation κ = 2.0 of CREST are very simila
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::379c003346a14a13548fe6abffdc54f8
https://doi.org/10.1088/0029-5515/40/3y/326
https://doi.org/10.1088/0029-5515/40/3y/326
Conceptual Design of a Water and Steam Cooled Blanket for the Compact Reversed Shear Tokamak Reactor
Autor:
Yuzo Fukai, Tomoaki Yoshida, Naoto Sekimura, Y. Asaoka, Akiyoshi Hatayama, K. Tomabechi, Kunihiko Okano, Seiji Mori, Seiichiro Yamazaki, Nobuyuki Inoue, Akira Kohyama, Yuichi Ogawa
Publikováno v:
Fusion Technology. 34:863-867
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b9287a2e4d5a5b0c55d35d491ec24e79
https://doi.org/10.13182/fst98-a11963720
https://doi.org/10.13182/fst98-a11963720
Autor:
T. Yamamoto, Yuichi Ogawa, T. Amano, K. Takemura, Nobuyuki Inoue, Y. Asaoka, K. Tokimatsu, Kunihiko Okano, Y. Murakami, K. Tomabechi, Tomoaki Yoshida, Ryoji Hiwatari
Publikováno v:
Scopus-Elsevier
We designed a volumetric neutron source for testing large-scale blanket components, based on a steady-state tokamak device with superconducting coils. It is found that a neutron flux of approximately 1.0 MW m −2 is available in the medium-size devi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9c74cb36857021eca7fb663459d2a1f9
https://doi.org/10.1016/s0920-3796(98)00169-0
https://doi.org/10.1016/s0920-3796(98)00169-0