Numerical simulation of two-phase flow in 44 simulated bundle

Ono, Ayako ; Yamashita, Susumu   ; Suzuki, Takayuki*; Yoshida, Hiroyuki  

JAEA is implementing the 3D detailed nuclear-thermal-coupled analysis code to analyze the transition state of the core and to reduce the likelihood of the design. In the development plan, the computational fluid dynamics code based on the VOF method, JUPITER, is applied for TH part of the 3D detailed nuclear-thermal-coupled analysis code.