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Kato, Atsushi; Kubo, Shigenobu; Chikazawa, Yoshitaka; Miyagawa, Takayuki*; Uchita, Masato*; Suzuno, Tetsuji*; Endo, Junji*; Kubo, Koji*; Murakami, Hisatomo*; Uzawa, Masayuki*; et al.
Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet), 11 Pages, 2022/04
The authors are carrying out conceptual design studies for a pool-type sodium-cooled fast reactor. There are main challenges such as measures against severe earthquake in Japan, thermal hydraulic in a reactor vessel (RV), a decay heat removal system design. When the JP-pool SFR of 650 MWe is installed in Japan, it shall be designed against the severe seismic conditions. Additionally, a newly three-dimensional seismic isolation system is under development.
Yamamoto, Toshihiro; Miyoshi, Yoshinori
Journal of Nuclear Science and Technology, 41(2), p.99 - 107, 2004/02
Times Cited Count：38 Percentile：90.02(Nuclear Science & Technology)A new algorithm of Monte Carlo criticality calculations for implementing Wielandt's method is developed. In this algorithm, part of fission neutrons emitted during random walk processes are tracked within the same generation, and thus a fission source distribution in the next generation spread more widely. Applying this method intensifies a neutron interaction effect even in a loosely-coupled array where conventional Monte Carlo criticality calculation methods have difficulties, and a converged fission source distribution can be obtained with fewer generations. Computing time spent for one generation, however, increases because of tracking fission neutrons within the same generation, which eventually results in an increase of total computing time up to convergence. However, since a fission source convergence is attained with fewer source iterations, a reliable determination of convergence can easily be made even in a system with a slow convergence.
Onuki, Akira; Nakamura, Hideo; Anoda, Yoshinari
Dai-7-Kai Doryoku Enerugi Gijutsu Shimpojiumu Koen Rombunshu (00-11), p.258 - 263, 2000/00
no abstracts in English
Tokuhiro, Akira; Kimura, Nobuyuki
JNC TN9400 2000-015, 26 Pages, 1999/09
JNC-TN9400-2000-015.pdf:1.43MB
The quantification of the rate-of-rise of the thermal stratification interface, a "thin" vertical zone where the temperature gradient is the steepest, is important in assessing the potential implications of thermally-induced stress problems in liquid-metal cooled reactors. Thermal stratification can likewise occur in confined volumes containing ordinary fluids (Pr
1), where there is an input of thermal convective energy. In the prominent case of liquid metal reactors, there have been many studies on quantifying the rate-of-rise of a defined stratification interface, in terms of one or more of the following dimensionless groups, mainly: Richardson (Ri), Reynolds (Re), Grashof (Gr), Rayleigh (Ra) and/or Froude (Fr) numbers. Stratification is also a transient process in the volume in question. In the present work the anthors presents a derivation based on order-of-magnitude analysis (OMA), including an sensible energy balance, that produces a new representation more consistent than p
Inagaki, Terumi*; Ishii, Toshimitsu; *
NDT & E International, 32(5), p.247 - 257, 1999/00
no abstracts in English
Koizumi, Koichi; Nakahira, Masataka; Oka, Kiyoshi; Obara, Kenjiro; *; Morita, Yosuke; Tada, Eisuke
JAERI-Tech 96-041, 66 Pages, 1996/10
no abstracts in English
Tomimitsu, Hiroshi; *; Aizawa, Kazuya; Yoshinari, Akira*
Journal of the Physical Society of Japan, 65(SUPPL.A), p.252 - 254, 1996/00
no abstracts in English
Miyo, Yasuhiko; Ogiwara, Norio; Saido, Masahiro; *; *
Shinku, 38(3), p.274 - 277, 1995/00
no abstracts in English
; C.A.Brebbia*
Kyokai Yosoho Kenkyukai BEM, Tekunoroji, Konfarensu Rombunshu, p.59 - 64, 1993/06
no abstracts in English
M.E.Kab*; Hayafune, Hiroki
PNC TN9410 92-018, 58 Pages, 1992/01
This report describes the result of the analysis of unprotected Loss of Flow (LOF) ansient experiment conducted at the PLANt Dynamics Test Loop (PLANDTL) experimentalfility by Super System Code (SSC) and SubAssembly Boiling EvolutioN Analysis (SABENA)ode. This report also describes the effect of the modification we made in SSC with t recent void fraction and two-phase friction multiplier models during the analysis othe experiment. After the analysis, it was found that the two-fluid two-phase flow mel of SABENA 1-D is better than the homogeneous model of SSC in predictiong the therhydraulic behavior within the simulated fuel bundle test section of thePLANDTL facily in case of high quality sodium boiling experiment. Moreover, it wasalso revealed tt the two-fluid one dimensional model is not accurate enough in predicting the onsetf boiling and axial evolution of boiling region inside the heatedchannel.
; C.A.Brebbia*
Engineering Analysis with Boundary Elements, 10, p.345 - 352, 1992/00
Times Cited Count：9 Percentile：73.03(Engineering, Multidisciplinary)no abstracts in English
JAERI 1288, 30 Pages, 1983/10
no abstracts in English
Tomimitsu, Hiroshi; Kamada, Koji*
Hyomen Kagaku, 4(1), p.35 - 40, 1983/00
no abstracts in English
;
JAERI-M 5590, 48 Pages, 1974/03
no abstracts in English
