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Uda, Minoru*; Iwadachi, Takaharu*; Uchida, Munenori*; Yamada, Hirokazu*; Nakamichi, Masaru*; Kawamura, Hiroshi
JAERI-Conf 2004-006, p.60 - 65, 2004/03
no abstracts in English
Monde, Masanori*; Mitsutake, Yuichi*; Ishida, Kenji*; Hino, Ryutaro
JAERI-Tech 2003-013, 56 Pages, 2003/03
no abstracts in English
Yonomoto, Taisuke; Otsu, Iwao; Nakamura, Hideo; Kondo, Masaya; Svetlov, S.*
Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.215 - 220, 2002/06
no abstracts in English
Kureta, Masatoshi; Akimoto, Hajime; Yamamoto, Kazuhiko*; Okada, Hiroyuki*
Proceedings of International Congress on Advanced Nuclear Power Plants (ICAPP) (CD-ROM), 7 Pages, 2002/00
no abstracts in English
Sakamoto, Shinichi; Meigo, Shinichiro; Konno, Chikara; Harada, Masahide; Miyake, Yasuhiro*; Kasugai, Yoshimi; Muto, Suguru*; Fujimori, Satoru*; Ono, Takehiro; Ikeda, Yujiro
JAERI-Tech 2001-075, 168 Pages, 2001/12
JAERI-Tech-2001-075.pdf:12.78MB
no abstracts in English
Takase, Kazuyuki
Proceedings of the 1st International Symposium on Advanced Fluid Information (AFI-2001), p.376 - 381, 2001/10
no abstracts in English
Takase, Kazuyuki
Fusion Engineering and Design, 49-50, p.349 - 354, 2000/11
Times Cited Count：6 Percentile：42.55(Nuclear Science & Technology)no abstracts in English
Hino, Ryutaro; Haga, Katsuhiro; ; ; *; Kaminaga, Masanori; Sudo, Yukio; *
JAERI-Tech 97-009, 50 Pages, 1997/03
no abstracts in English
Ota, Mitsuru
Nihon Kikai Gakkai-Shi, 98(922), p.759 - 761, 1995/09
no abstracts in English
Nakamura, H.; ; *; *
JAERI-M 85-007, 30 Pages, 1985/02
no abstracts in English
Tone, Tatsuzo
Nihon Kikai Gakkai-Shi, 87(782), p.95 - 100, 1984/00
no abstracts in English
; ; ; ; Matsuda, Shinzaburo; *; Ohara, Yoshihiro;
JAERI-M 83-069, 30 Pages, 1983/05
no abstracts in English
Yamamoto, Masaya; Sekine, Takashi; Yoshida, Akihiro
no journal, ,
Beyond design basis accident have been evaluated in Joyo. Anticipated transient without scram, loss of reactor level and protected loss of heat sink are identified as main accident sequence group. Unprotected transient over power and protected loss of heat sink are selected as representative accident by the view point of frequency and impact. As the result of safety analysis of these accident, we confirmed that no beyond design basis accident reach to release a large amount of radioactive materials.
Kikuchi, Mitsuru
no journal, ,
DEMO is an important milestone for fusion research. The power handling becomes a highlight toward DEMO. A tokamak plasma with strongly negative triangularity may offer such an opportunity as an innovative concept. While this configuration is magnetic hill, recent MHD stability calculation shows reasonable beta limit (beta_N=3.2) without wall stabilization. In this paper, we discuss favorable and critical issues of such configuration in both physics and technology.
Kikuchi, Mitsuru
no journal, ,
The negative triangular plasma is proposed as one of methods for the heat load solution in the magnetic confinement fusion. The ST is easier to implement negative triangular plasma and we discuss such a possibility.
Yamada, Fumiaki; Mori, Takero
no journal, ,
The core cooling by the nature circulation was effective, that evaluated the form of the circulation root of various coolant in the failure of forced circulation of main heat transport system which was an accident sequence of loss of heat removal system more than design basis accident of the FBR from plant dynamics characteristic analysis.
Kurisaka, Kenichi; Nishino, Hiroyuki; Sotsu, Masutake
no journal, ,
In the sodium-cooled fast reactor, we proposed redundant and independent safety measures to prevent loss of heat removal against failure of the design-based-accident countermeasures. By considering those safety measures, we implemented deterministic evaluation of their effectiveness and probabilistic study on reduction of the occurrence frequency of loss-of-heat-removal. As a result, we obtained prospect to prevent loss-of-heat-removal with robust measures.
