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Soma, Shu; Ishigaki, Masahiro*; Abe, Satoshi; Shibamoto, Yasuteru
Nuclear Engineering and Technology, 10 Pages, 2024/00
Doda, Norihiro; Araseki, Hideo; Nabeshima, Kunihiko; Takata, Takashi; Tanaka, Masaaki; Ohshima, Hiroyuki
no journal, ,
JAEA has started the development of a multi-level plant simulation system as a powerful tool for the design studies of sodium-cooled fast reactors. This system enables from highly-efficient to highly-accurate analyses of various operating statuses including normal operation, abnormal transient and accidents by employing multi-level models, and is able to respond flexibly to most of the design options. The conceptual design of the new system, the coupling method of codes as a key of the system development, and the development plan are reported in this presentation.
Asahi, Yoshimitsu; Shimamura, Keisuke; Kobayashi, Hidekazu; Kodaka, Akira; Morikawa, Yo
no journal, ,
no abstracts in English
Yoshimura, Kazuo; Doda, Norihiro; Oki, Hiroshi*; Fujisaki, Tatsuya*; Tanaka, Masaaki; Vilim, R. B.*
no journal, ,
The CFD analysis of SHRT-17 test in the experimental fast bread reactor of EBR-II, was carried out to investigate the thermal stratification measured in the core upper plenum with the simulation result in the test. From the numerical simulation, it could be confirmed that the driving force of the natural circulation through the whole plant was influenced by the thermal stratification in the upper part of the core upper plenum and in the sloped part of the Z-shaped pipe.
Horiguchi, Naoki; Uesawa, Shinichiro; Yoshida, Hiroyuki
no journal, ,
Evaluation method based on CFD and particle tracking method for aerosol particle depositon in a reactor building during severe accident has been developed. In order to construct of prediction model of particle deposition in a narrow channel for reduction of numerical simulation cost in the evaluation method, some numerical simulations with each representative components of the narrow channel, a straight, a bend, a nozzle and a diffuser part were conducted. In case of the bend part, behavior of air and CsI particles under steady flow were simulated with parameters, particle diameter, pressure difference between inlet and outlet of a modeled channel and width of the channel. As results of particle deposition rate based on the numerical simulation, increase tendences of particle depositon rate with increase of particle diameter were changed with increase of pressure difference and decrease of width. These results can be important knowledge for the modelling.
Yoshimura, Kazuo; Doda, Norihiro; Fujisaki, Tatsuya*; Igawa, Kenichi*; Tanaka, Masaaki
no journal, ,
In the ULOHS tests performed in the experimental fast reactor U.S. EBR-II, the thermal stratification in the cold pool (CP) has influence on the whole plant behavior during the events because the secondary sodium pump tripped without scram nor tripping the primary pumps. In order to create the one-dimensional model for the CP of the plant dynamics analysis code, the multi-dimensional thermal hydraulics analyses using computational fluid dynamics (CFD) code were conducted to investigate the thermal hydraulics phenomena in the CP. It was found by comparison with the experimental data that the modeling of the detail sodium flow at the outlet of the intermediate heat exchanger, the leakage flow from the inner components to the cold pool, and the heat radiation from the CP to the atmosphere was important to the evaluation of the thermal stratification.
