A Pressrised Heavy Water Reactor (PHWR) Coolant Channel Simulation of the Atucha II Nuclear Power Plant

Abstract

The coolant channel components and fuel assembly of the Atucha II PHWR nuclear power plant were simulated. 3D CFD simulation was used for estimating the pressure drop and the flow field around detailed models of one of the spacers and the channel outlet throttle port. Results allow for a deep understanding of the channel flow and the frictional and form pressure losses inside the channel. Results were compared with experimental data for a simplified spacer and correlations for the pressure drop from literature were also implemented obtaining good agreement.