Validation of Subchannel Code Kamui: Analysis of Outlet Temperature Profiles of a 19-Pin Test Assembly

Abstract

Thermal hydraulic analysis of a Sodium-cooled Fast Reactor test assembly has been performed by employing subchannel analysis code KAMUI. The code has been updated by incorporating some recent physical models for pressure drop and coolant mixing. Performance of several conventional flow resistance and mixing models was assessed, by comparing predicted outlet temperature profiles against available experimental data. The calculations were carried out for high, transitional, and low Reynolds number regions. The prediction capability of the code for a wire-wrapped bundle has been successfully demonstrated in this paper.