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Moriyama, Kiyofumi; Nakamura, Hideo; Maruyama, Yu*
Nuclear Engineering and Design, 236(19-21), p.2010 - 2025, 2006/10
Times Cited Count：25 Percentile：82.66(Nuclear Science & Technology)A computer code JASMINE-pre was developed for the prediction of premixing conditions of fuel-coolant interactions and the debris bed formation behavior relevant to severe accidents of light water reactors. JASMINE-pre consists of three melt component models: melt jet, melt particles and melt pool, coupled with a two-phase flow model derived from the ACE-3D code developed at JAERI. Simulations of the FARO corium quenching experiments with a saturated water pool and with a subcooled water pool were performed with JASMINE-pre and 
. JASMINE-pre reproduced the pressurization and fragmentation behaviors observed in the experiments with a reasonable accuracy. The results by pmjet showed qualitatively the same trend with JASMINE-pre in the fragmentation behavior.
; ; ; ; ; Ogasawara, Shinobu*; Adachi, Masaaki*; ; Kume, Etsuo
JAERI-Data/Code 99-026, 91 Pages, 1999/05
JAERI-Data-Code-99-026.pdf:2.9MB
no abstracts in English
Fukuda, Takanari; Yoshida, Hiroyuki; Kamiya, Tomohiro; Suzuki, Takayuki*; Tada, Kenichi; Nagaya, Yasunobu
no journal, ,
JAEA has been engaged in the development of JAMPAN, a platform for multi-physics simulations, to enable the numerical simualtons for enhancing the quality and safety of the light water reactor design. In this study, ACE-3D, which is based on a three-dimensional two-fluid model capable of general-purpose multidimensional thermal-hydraulic calculations, was selected as the thermal-hydraulic calculation code. Furthermore, a JAMPAN module was developed to facilitate a coupled MVP/ACE-3D neutronics/thermal-hydraulics simulation. In the presentation, the results of the simulation for an 8
8 BWR fuel assembly with JAMPAN will be presented.
Liong, C.*; Yamamoto, Akio*; Endo, Tomohiro*; Tada, Kenichi
no journal, ,
The purpose of this study is to apply neutronics thermal-hydraulics coupling scheme between the three-dimensional heterogeneous neutronics analysis code GenesisRPC and the JAEA-developed subchannel analysis code ACE-3D. As a test case, a simplified BWR 
assembly is used to perform the coupled simulation. The three-dimensional pin-by-pin power, pin-by-pin subchannel-wise coolant temperature, and void distributions were calculated.
Horiguchi, Naoki; Yoshida, Hiroyuki; Nakao, Yasuhiro*; Kanagawa, Tetsuya*; Kaneko, Akiko*; Abe, Yutaka*
no journal, ,
no abstracts in English
Yoshida, Hiroyuki; Horiguchi, Naoki
no journal, ,
In a severe accident in nuclear reactors, fuel debris is assumed to migrate and exist in porous media due to the solidification of molten fuel and other materials. Therefore, evaluating the thermal-hydraulic behavior in the porous media is necessary to understand the transition of severe accidents in nuclear reactors. In the severe accident of nuclear reactors, it is considered that various kinds of flow behaviors appear in the porous media, and it is essential to evaluate the two-phase flow behavior in the porous media to study the fuel debris temperature rise and remelting. Therefore, we are developing a multiphase CFD numerical simulation method based on the three-dimensional two-fluid model. This report describes the outline of the multiphase CFD numerical simulation method based on a three-dimensional two-fluid model and the analytical results.
Yoshida, Hiroyuki; Nagatake, Taku; Nemoto, Yoshiyuki; Kaji, Yoshiyuki
no journal, ,
