Introductory CFD Analysis of the SLOWPOKE-2 and Neutron Flux Analysis

Abstract

Currently, the thermal power of the SLOWPOKE-2 reactor at Royal Military College is a “best estimate” determined by historical data and/or a scaling factor of the neutron flux. In order to accurately calculate the thermal power of the reactor based on measurable operating parameters, such as inlet and outlet coolant temperature, a computational fluid dynamic (CFD) model of the SLOWPOKE-2 core is being created. Accurate determination of thermal power in tandem with neutron flux data should provide enhanced fuel monitoring capabilities in the SLOWPOKE-2 facility. Progress on development of the CFD model, along with available preliminary results, will be presented.