Preliminary Thermodynamics and Neutronics Analysis of Canadian Nuclear Battery

Abstract

The Canadian Nuclear BatteryTM (CNB) is a 2400 kWth (500 kWe) small modular reactor (SMR) initially designed in the 1980s targeted at applications in remote locations in Northern Canada [1]–[3]. The reactor uses potassium or sodium heat pipes as the primary heat removal system which demonstrate passive cooling characteristics. Heat pipes are metal pipes filled with working liquid and its vapour phase to transfer heat from the heated area (evaporator section) to the cooled area (condenser section) through phase change. Theoretical investigations are carried out to produce adequate information for the effective utilization of the heat pipe design in the reactor. Steady-state and a hypothetical double-power transient are simulated with STAR-CCM+ to understand the thermodynamics of the core and the propagation of heat pipe failures in accidental events. Preliminary neutronics calculations are carried out for the hypothetical double power transient and 50% power setback transient to evaluate the neutronics and xenon behaviours of the reactor. The purpose of the study is to provide first information about the thermal and neutronics performances of CNB in the early stage of development.