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Kikuchi, Mitsuru; Tamai, Hiroshi; Matsukawa, Makoto; Fujita, Takaaki; Takase, Yuichi*; Sakurai, Shinji; Kizu, Kaname; Tsuchiya, Katsuhiko; Kurita, Genichi; Morioka, Atsuhiko; et al.
Nuclear Fusion, 46(3), p.S29 - S38, 2006/03
Times Cited Count：13 Percentile：41.76(Physics, Fluids & Plasmas)The National Centralized Tokamak (NCT) facility program is a domestic research program for advanced tokamak research to succeed JT-60U incorporating Japanese university accomplishments. The mission of NCT is to establish high beta steady-state operation for DEMO and to contribute to ITER. The machine flexibility and mobility is pursued in aspect ratio and shape controllability, feedback control of resistive wall modes, wide current and pressure profile control capability for the demonstration of the high-b steady state.
Tani, Keiji; Tobita, Kenji; Iio, Shunji*; Tsutsui, Hiroaki*; Nishio, Satoshi; Aoki, Takayuki*
Denki Gakkai Rombunshi, A, 125(11), p.938 - 942, 2005/11
Studies on the loss of fusion produced alpha particles enhanced by toroidal field (TF) ripple in a low-aspect-ratio tokamak reactor (VECTOR) have been made by using an orbit-following Monte-Carlo code. The ripple loss is strongly reduced as the aspect ratio becomes low. Consequently, alpha particles are well confined in VECTOR. Thanks to the good confinement of alphas in a low-aspect-ratio system, the number of TF coils can be reduced to about 6, one half of the original VECTOR, by installing cooling systems near the outer edge of plasma and making allowances for about 30% increase in the bore diameter of TF coils.
Sakai, Takuro; Sato, Takahiro; Ishii, Yasuyuki; Oikawa, Masakazu*; Shimada, Hirofumi*; Haga, Junji*
Dai-18-Kai Tandemu Kasokuki Oyobi Sono Shuhen Gijutsu No Kenkyukai Hokokushu, p.73 - 76, 2005/10
no abstracts in English
Song, Y.*; Nishio, Satoshi
Fusion Engineering and Design, 72(4), p.345 - 362, 2005/01
Times Cited Count：6 Percentile：40.47(Nuclear Science & Technology)This paper presents detailed optimization results and design windows for the engineering design of normal conducting (NC) center post based on the analysis of thermal-hydraulic, static stress and critical buckling. At the same time a method to reduce the stress in the center post have been proposed, which can be applied to enhance the possibility of normal conducting center post in the future power plants. When the method of improvement for reducing the stress is applied in the system of the center post, the maximum magnet field can be improved from 8.6T to 15T.
analyses with ferromagnetic and plasma rotation effects and wall geometry for a high steady state tokamakKurita, Genichi; Bialek, J.*; Tsuda, Takashi; Azumi, Masafumi; Ishida, Shinichi; Navratil, G. A.*; Sakurai, Shinji; Tamai, Hiroshi; Matsukawa, Makoto; Ozeki, Takahisa; et al.
IAEA-CN-116/FT/P7-7 (CD-ROM), 8 Pages, 2004/11
The critical beta is shown to be decreased by ferromagnetic effect by about 8 % for m/m0
2, m and m0 denote the permeability of ferromagnetic wall and vacuum, respectively, for tokamak of aspect ratio 3. The existence of the stability window opened by both effects of the toroidal plasma rotation and the plasma dissipation, which was not observed for high aspect ratio tokamak, is found for tokamak of aspect ratio 3. The effect of ferromagnetism on them is also investigated. The critical beta analyses of NCT (National Centralized Tokamak) plasma using VALEN code are started with stabilizing plate and vacuum vessel geometry with finite resistivity, and the results for passive effect of stabilizing plate are obtained. The calculations including stabilizing effect of the vacuum-vessel and also active feedback control are also performed for present design of NCT plasma.
Sakurai, Shinji; Tobita, Kenji; Nishio, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.955 - 958, 2004/11
no abstracts in English
Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi
Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.952 - 954, 2004/11
Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.
Tobita, Kenji; Nishio, Satoshi; Konishi, Satoshi*; Jitsukawa, Shiro
Journal of Nuclear Materials, 329-333(Part2), p.1610 - 1614, 2004/08
Times Cited Count：12 Percentile：61.53(Materials Science, Multidisciplinary)no abstracts in English
Tobita, Kenji; Ozeki, Takahisa; Nakamura, Yukiharu
Plasma Physics and Controlled Fusion, 46(7), p.S95 - S105, 2004/07
Times Cited Count：10 Percentile：32.04(Physics, Fluids & Plasmas)no abstracts in English
Nishio, Satoshi
Denki Gakkai Purazuma Kenkyukai Shiryo (PST-03-37), p.1 - 6, 2003/10
no abstracts in English
Tani, Keiji; Tobita, Kenji; Nishio, Satoshi; Iio, Shunji*; Tsutsui, Hiroaki*; Aoki, Takayuki*
Denki Gakkai Purazuma Kenkyukai Shiryo (PST-03-39), p.13 - 18, 2003/09
Studies were made on ripple losses of fusion produced alpha particles in a tokamak reactor with a non-circular plasma cross-section by using an orbit-following Monte-Carlo code. A preliminary estimation of ripple loss of alpha particles in VECTOR, a compact tokamak type fusion reactor, with a negative magnetic shear was also made
Sengoku, Seio
Denki Gakkai Purazuma Kenkyukai Shiryo (PST-03-41), p.23 - 26, 2003/09
no abstracts in English
Song, Y.; Nishio, Satoshi
Proceedings of 20th IEEE/NPSS Symposium on Fusion Engineering (SOFE 2003), p.581 - 584, 2003/00
no abstracts in English
Watanabe, Tadashi
Parallel Computational Fluid Dynamics, p.33 - 40, 1998/00
no abstracts in English
Nishio, Satoshi; Ueda, Shuzo; Seki, Yasushi
Denki Gakkai Genshiryoku Kenkyukai Shiryo, p.21 - 28, 1997/00
no abstracts in English
Nishio, Satoshi; Ueda, Shuzo; Aoki, Isao; Kuroda, Toshimasa*; Miura, H.*; Kurihara, Ryoichi; Kunugi, Tomoaki; Seki, Yasushi
Fusion Energy 1996, 3, p.693 - 699, 1997/00
no abstracts in English
M.Z.Hasan*; Takase, Kazuyuki
15th IEEE/NPSS Symp. on Fusion Engineering,Vol. 1, 0, p.1202 - 1205, 1993/00
no abstracts in English
Takase, Kazuyuki
Ryutai Kogaku Bumon Koenkai Koen Rombunshu, p.266 - 268, 1993/00
no abstracts in English
Ninomiya, Hiromasa; JT-60 Team
Phys. Fluids B, 4(7), p.2070 - 2080, 1992/07
Times Cited Count：53 Percentile：82.97(Physics, Fluids & Plasmas)no abstracts in English
Ohara, Yoshihiro; *
JAERI-M 5929, 20 Pages, 1974/12
no abstracts in English
