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pro vyhledávání: '"J Ohmori"'
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Autor:
M. Nakahira, K. Shimizu, J. Ohmori, Yukinori Usui, Masanori Onozuka, K. Shibanuma, K. Urata, Nobukazu Takeda, Yoshihiro Tsujita, Satoshi Kakudate
Publikováno v:
Fusion Engineering and Design. 82:2081-2088
Demonstration tests for manufacturing and assembly of the International Thermonuclear Experimental Reactor (ITER) vacuum vessel have been conducted to confirm manufacturing and assembly process of the vacuum vessel (VV). The full-scale partial mock-u
Autor:
K Tobita, S Nishio, M Sato, S Sakurai, T Hayashi, Y.K Shibama, T Isono, M Enoeda, H Nakamura, S Sato, K Ezato, T Hirose, S Ide, T Inoue, Y Kamada, Y Kawamura, H Kawashima, N Koizumi, G Kurita, Y Nakamura, K Mouri, T Nishitani, J Ohmori, N Oyama, K Sakamoto, S Suzuki, T Suzuki, H Tanigawa, K Tsuchiya, D Tsuru
Publikováno v:
Nuclear Fusion. 47:892-899
The concept for a compact DEMO reactor named 'SlimCS' is presented. Distinctive features of the concept are low aspect ratio (A = 2.6) and use of a reduced-size centre solenoid (CS) which has the function of plasma shaping rather than poloidal flux s
Autor:
J. Ohmori, Masayoshi Sugihara, V.E. Lukash, R.R. Khayrutdinov, K. Ioki, Michiya Shimada, Yasunori Kawano, Yu. Gribov, H. Fujieda
Publikováno v:
Nuclear Fusion. 47:337-352
The impacts of plasma disruptions on ITER have been investigated in detail to confirm the robustness of the design of the machine to the potential consequential loads. The loads include both electro-magnetic (EM) and heat loads on the in-vessel compo
Autor:
Mikio Enoeda, Hideo Nakamura, M. Sato, Yoshinori Kawamura, J. Ohmori, Daigo Tsuru, S. Nishio, T. Kuroda, Takanori Hirose, Kenji Tobita, Satoshi Sato
Publikováno v:
Fusion Engineering and Design. 81:1271-1276
Our idea on the DEMO plant is that it must demonstrate (1) an electric power generation of one GW level, (2) self-sufficiency of tritium fuel (TBR is more than 1.05), (3) year-long continuous operation, etc. At the same time, DEMO is expected to use
Publikováno v:
Fusion Engineering and Design. 81:443-448
Recent progresses of the first wall (FW) and blanket design are reported in this paper. Considering the plasma-wall interaction, especially the halo current distribution, a multi-facetted surface shape of the inboard FW panel has been optimized. More
Autor:
K. Tobita, S. Nishio, M. Enoeda, M. Sato, T. Isono, S. Sakurai, H. Nakamura, S. Sato, S. Suzuki, M. Ando, K. Ezato, T. Hayashi, T. Hirose, T. Inoue, Y. Kawamura, N. Koizumi, Y. Kudo, R. Kurihara, T. Kuroda, M. Matsukawa, K. Mouri, Y. Nakamura, M. Nishi, Y. Nomoto, J. Ohmori, N. Oyama, K. Sakamoto, T. Suzuki, M. Takechi, H. Tanigawa, K. Tsuchiya, D. Tsuru
Publikováno v:
Fusion Engineering and Design. 81:1151-1158
Three options of fusion DEMO plant are proposed characterized by functions of the center solenoid (CS). The prime option uses a downsized CS, which does not provide sufficient V-s for plasma current ramp-up but supplies enough coil current for plasma
Autor:
M. Nakahira, W. Daenner, T. Kuroda, Yu. Utin, S. Maruyama, V.N. Tanchuk, S Kajiura, S. Chiocchio, Masato Akiba, P. Lorenzetto, N Miki, M. Morimoto, Masanori Onozuka, J Ohmori, G. Federici, P. Barabaschi, F. Elio, Kazuyoshi Sato, L. Jones, Mikio Enoeda, Y. Strebkov, V. Barabash, R. Tivey, Koichiro Ezato, Mario Merola, V. A. Krylov, A. Gervash, K. Ioki, S. Suzuki, V. Rozov, D. Grebennikov
Publikováno v:
Journal of Nuclear Materials. :31-38
Progress has been made in the preparation of the procurement specifications for key nuclear components of ITER. Detailed design of the vacuum vessel (VV) and in-vessel components is being performed to consider fabrication methods and non-destructive
Publikováno v:
The Proceedings of the Materials and Mechanics Conference. 2010:227-229
Publikováno v:
IEEE Transactions on Appiled Superconductivity. 10:576-579
The central solenoid (CS) coil of the Reduced Technical Objective/Reduced Cost (RTO/RC) ITER is structurally independent from the toroidal magnet system and consists of 6 modules. The Nb/sub 3/Sn superconducting cable is a similar design to that of t