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Kawanishi, Tomohiro; Nagaya, Yasunobu; Yoshida, Hiroyuki; Akie, Hiroshi; Tada, Kenichi; Ono, Ayako
no journal, ,
JAEA has started to develop the advanced neutronics/thermal-hydraulics coupling simulation system for improvement of the light water reactor analysis and safety. This simulation system uses a continuous energy Monte Carlo calculation code MVP and CFD calculation code TPFIT and JUPITER. The advanced system can treat rigorous bubble shape and it does not adopt the approximate expression and empirical formula. The advanced system will be a reference system for the current neutronics/thermal-hydraulics coupling simulation system. In this presentation, we show the outline of the advanced system.
Tada, Kenichi; Akie, Hiroshi; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki; Kawanishi, Tomohiro
no journal, ,
JAEA has started to develop the advanced neutronics/thermal-hydraulics coupling simulation system for improvement of the light water reactor analysis and safety. We developed a prototype simulation system to find the issues of coupling simulation and to investigate the optimum mesh size for neutronics and thermal-hydraulics analysis. This presentation explains the overview of the prototype simulation system and its calculations results.
Akie, Hiroshi; Tada, Kenichi; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki; Kawanishi, Tomohiro
no journal, ,
Japan Atomic Energy Agency is developing an advanced neutronics/thermal-hydraulics coupling simulation system for the design advancement and the safety improvement of light water reactors. In this presentation, an impact of the fine-scale void distribution in sub-channels on neutronics calculations is studied.
Tada, Kenichi; Akie, Hiroshi; Kamiya, Tomohiro; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki; Kawanishi, Tomohiro
no journal, ,
JAEA is developing the advanced neutronics/thermal-hydraulics coupling simulation system to improve the design and safety analysis of light water reactors. This presentation explains the coupling simulation system using a continuous energy Monte Carlo code MVP and a subchannel analysis code NASCA.
Tada, Kenichi; Akie, Hiroshi; Kamiya, Tomohiro; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
We implemented the handling module for the subchannel analysis code NASCA on the multi-physics platform JAMPAN. This function is used for the neutronics/thermal-hydraulics coupling simulation. The MVP/NASCA coupling calculation on JAMPAN will be applied to the large-scale calculation e.g., a whole core analysis. The calculation results of JAMPAN were compared to those of the prototype simulation system IPACS. The calculation results of JAMPAN showed good agreement with those of IPACS.
Yoshida, Hiroyuki; Kamiya, Tomohiro; Tada, Kenichi
no journal, ,
no abstracts in English
Tada, Kenichi; Kondo, Ryoichi; Kamiya, Tomohiro; Nagatake, Taku; Ono, Ayako; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
JAEA has developed the multi-physics platform JAMPAN. In the previous presentation, we demonstrated a BWR single fuel assembly calculation by the coupling calculation of the continuous energy Monte Carlo calculation code MVP and the subchannel analysis code NASCA. The final goal of the MVP/NASCA coupling calculation is the whole core analysis. To achieve this, we implemented the flow rate calibration function in JAMPAN for the MVP/NASCA coupling calculation of the BWR multi-fuel assembly geometry.
Kamiya, Tomohiro; Nagatake, Taku; Ono, Ayako; Tada, Kenichi; Kondo, Ryoichi; Nagaya, Yasunobu; Yoshida, Hiroyuki
no journal, ,
JAEA has developed a platform JAMPAN for multi-physics simulations, has improved a neutronics analysis code, and has improved and validated thermal-hydraulics analysis codes to improve the design and the safety of light water reactors. The objective is implementing the coupling modules between the neutronics code MVP and the thermal-hydraulics code JUPITER, and verifying the modules. A fuel bundle geometry under a normal operation condition of a BWR was used for the neutronics and thermal-hydraulics coupling simulation to verify the modules. In this presentation, we will explain how to send and receive data between MVP and JUPITER through JAMPAN and show the results of the neutronics/thermal-hydraulics coupling simulations using MVP and JUPITER.