Numerical simulation of thermal-hydraulic phenomena in fast reactor, 3; Development of Numerical estimation method for unsteady thermal-hydraulic phenomena in primary cooling system

Tanaka, Masaaki  ; Murakami, Satoshi*; Fujisaki, Tatsuya*; Oki, Hiroshi*; Ohno, Shuji  ; Kamide, Hideki 

Numerical estimation method to analyze unsteady flow phenomena in the upper plenum and the hot-leg piping system in sodium cooled fast reactor has been developed. As for the high cycle thermal fatigue, outline of development status of a numerical simulation code MUGTHES and numerical estimation method including V&V process are explained. As for the flow-induced vibration phenomena, construction of a numerical model of the hot-leg piping integrated into a symmetric half domain of the upper plenum is explained and numerical results relating to applicable numerical schemes and turbulence model (RSM) are briefly mentioned.