Development of design technology on thermal-hydraulic performance in tight-lattice rod bundles, 4; Numerical evaluation of fluid mixing phenomena using advanced interface-tracking method

Yoshida, Hiroyuki  ; Nagayoshi, Takuji*; Takase, Kazuyuki; Akimoto, Hajime

Thermal-hydraulic design of the current boiling water reactor (BWR) is performed by correlations with empirical results of actual-size tests. Development of a method that enables the thermal-hydraulic design of nuclear rectors without these actual size tests is desired, because these tests take a long time and entail great cost. For this reason we developed an advanced thermal-hydraulic design method for FLWRs using innovative two-phase flow simulation technology. In this study, detailed two-phase flow simulation code using advanced interface tracking method: TPFIT is developed to get the detailed information of the two-phase flow. We tried to verify the TPFIT code comparing with the 2-channel air-water and steam-water mixing experimental results.