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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.
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.