Abstract
Three-dimensional large-scale numerical simulations were carried out to predict the complicated two-phase flow characteristics in a fuel bundle of an advanced light water reactor. Conventional analysis methods with a two-fluid model need composition equations and empirical correlations based on the experimental data. Therefore, it is difficult to obtain high prediction accuracy when experimental data are nothing. Then, a new two-phase flow analysis method was proposed and the TPFIT code was developed. This paper describes the predicted two-phase flow behavior in the simulated fuel channels with the TPFIT code, and the predicted liquid film behavior around a curved fuel rod with the FLUENT code which is one of the most famous commercial codes. In addition, flow visualization experiments were carried out to understand the liquid film behavior on the curved fuel rod. These results reflect the thermal design of the advanced light water reactor core.
