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Honda, Mitsuru; Ide, Shunsuke; Takizuka, Tomonori*; Hayashi, Nobuhiko; Yoshida, Maiko; Yagi, Masatoshi; Fujita, Takaaki
Nuclear Fusion, 53(7), p.073050_1 - 073050_11, 2013/07
Times Cited Count：22 Percentile：69.61(Physics, Fluids & Plasmas)Yagi, Masatoshi; Shimizu, Katsuhiro; Takizuka, Tomonori; Honda, Mitsuru; Hayashi, Nobuhiko; Hoshino, Kazuo; Fukuyama, Atsushi*
Contributions to Plasma Physics, 52(5-6), p.372 - 378, 2012/06
Times Cited Count：5 Percentile：21.93(Physics, Fluids & Plasmas)Shimizu, Katsuhiro; Takizuka, Tomonori; Hoshino, Kazuo; Honda, Mitsuru; Hayashi, Nobuhiko; Takayama, Arimichi*; Fukuyama, Atsushi*; Yagi, Masatoshi*
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 6 Pages, 2011/03
We have developed a self-consistent integrated modelling of core and SOL/divertor transport. Thereby it enables us to investigate operation scenarios to be compatible with high confinement core plasma and detached divertor plasmas. To integrate a 1.5D core code (TOPICS-IB and TASK) and a 2D divertor code (SONIC), we introduce a new Multiple Program Multiple Data parallel computing system. For an integrated code including Monte-Carlo calculations, this system makes it possible to perform efficient simulations. The predictive simulation studies are carried out for JT-60SA with the integrated code (TOPICS-IB/SONIC) and the characteristics of the divertor heat load after the H-mode transition is clarified. We also discuss about the temporal behavior of divertor characteristics after an ELM crash.
Tobita, Kenji; Nishio, Satoshi*; Enoeda, Mikio; Nakamura, Hirofumi; Hayashi, Takumi; Asakura, Nobuyuki; Uto, Hiroyasu; Tanigawa, Hiroyasu; Nishitani, Takeo; Isono, Takaaki; et al.
JAEA-Research 2010-019, 194 Pages, 2010/08
JAEA-Research-2010-019-01.pdf:48.47MBJAEA-Research-2010-019-02.pdf:19.4MB
This report describes the results of the conceptual design study of the SlimCS fusion DEMO reactor aiming at demonstrating fusion power production in a plant scale and allowing to assess the economic prospects of a fusion power plant. The design study has focused on a compact and low aspect ratio tokamak reactor concept with a reduced-sized central solenoid, which is novel compared with previous tokamak reactor concept such as SSTR (Steady State Tokamak Reactor). The reactor has the main parameters of a major radius of 5.5 m, aspect ratio of 2.6, elongation of 2.0, normalized beta of 4.3, fusion out put of 2.95 GW and average neutron wall load of 3 MW/m
. This report covers various aspects of design study including systemic design, physics design, torus configuration, blanket, superconducting magnet, maintenance and building, which were carried out increase the engineering feasibility of the concept.
Zn
Takeuchi, Tetsuya*; Yasui, Shinichi*; Toda, Masatoshi*; Matsushita, Masaki*; Yoshiuchi, Shingo*; Oya, Masahiro*; Katayama, Keisuke*; Hirose, Yusuke*; Yoshitani, Naohisa*; Honda, Fuminori*; et al.
Journal of the Physical Society of Japan, 79(6), p.064609_1 - 064609_15, 2010/06
Times Cited Count：42 Percentile：83.7(Physics, Multidisciplinary)ZnYoshiuchi, Shingo*; Toda, Masatoshi*; Matsushita, Masaki*; Yasui, Shinichi*; Hirose, Yusuke*; Oya, Masahiro*; Katayama, Keisuke*; Honda, Fuminori*; Sugiyama, Kiyohiro*; Hagiwara, Masayuki*; et al.
Journal of the Physical Society of Japan, 78(12), p.123711_1 - 123711_4, 2009/12
Times Cited Count：39 Percentile：82.77(Physics, Multidisciplinary)Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.
Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07
Times Cited Count：137 Percentile：97.72(Physics, Fluids & Plasmas)Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).
Yamasaki, Hiro*; Honda, Satoshi*; Ueda, Masashi; Endo, Akira*; Fueki, Manabu*
Keisoku Jido Seigyo Gakkai Rombunshu, 43(9), p.756 - 761, 2007/09
A non-intrusive temperature sensing system is proposed. It is developed for temperature measurement of liquid sodium coolant in fast breeder reactor. Liquid sodium is used as coolant due to high heat flux density in the reactor core. In this paper, the results of our feasibility study by 2-dimensional numerical simulation, small size experimental test done by Japan Atomic Energy Agency Oarai Institute, and theoretical analysis are described. The basic principle of temperature measurement is resistant thermometry of liquid sodium. The resistivity of liquid sodium is quite lower than that of the stainless steel (SUS304), which is used in the pipe wall. The resistivity temperature coefficient of liquid sodium(0.337%/deg) is higher than that of stainless steel(0.0865%/deg). If we feed electric current perpendicular to the axis of flow pipe, the current penetrates the pipe wall and flow across the liquid. The current concentrates the liquid sodium, only small portion of the current flows along the pipe wall. The electric potential distribution is almost dominated by resistivity of sodium. The potential distribution can be measured along the out side of the pipe wall. The potential difference between two fixed points on the pipe wall indicates the resistivity of sodium So the sodium temperature can be measured by potential difference. Measurement accuracy of 
5
C is obtained in experimental tests. Better estimation data are obtained by theoretical analysis using three dimensional model.
Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01
no abstracts in English
Shibanuma, Kiyoshi; *; *; *; Okawa, Yoshinao; *; Tada, Eisuke; Koizumi, Koichi; *; Nishio, Satoshi; et al.
JAERI-M 91-080, 357 Pages, 1991/06
no abstracts in English
Yamamoto, Shin; Ohara, Yoshihiro; Tani, Keiji; Nishio, Satoshi; Okumura, Yoshikazu; Araki, Masanori; Azumi, Masafumi; R.S.Devoto*; Fujisawa, Noboru; Hitoki, Shigehisa*; et al.
JAERI-M 88-086, 183 Pages, 1988/05
no abstracts in English
*; *; *; Adachi, Junichi*; *; *; *; Kuroda, Toshimasa*; *; *; et al.
JAERI-M 88-083, 426 Pages, 1988/05
no abstracts in English
Mizoguchi, Tadanori*; Iida, Hiromasa; Sugihara, Masayoshi; Fujisawa, Noboru; *; *; *; Nakajima, Kunihiko*; Nishio, Satoshi; *; et al.
JAERI-M 88-062, 77 Pages, 1988/03
no abstracts in English
Tone, Tatsuzo; Shiraishi, K.; ; ; *; ; *; *; *; *; et al.
JAERI-M 82-179, 49 Pages, 1982/11
no abstracts in English
; ; ; *; *; *; *; *; *; *; et al.
JAERI-M 82-176, 263 Pages, 1982/11
no abstracts in English
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Journal of Nuclear Materials, 48(2), p.207 - 209, 1973/02
Times Cited Count：2no abstracts in English
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Tanso, (72), p.14 - 20, 1973/00
no abstracts in English
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Tanso, (75), p.131 - 132, 1973/00
no abstracts in English
; ; *
Tanso, (75), p.136 - 138, 1973/00
no abstracts in English
C; Effect on electrical resistivity and thermal conductivity;
Journal of Nuclear Materials, 45(1), p.79 - 81, 1972/01
Times Cited Count：2no abstracts in English
