Thermalhydraulic and Thermal Analysis Methodology of the CANDU-3 Reactor Endshield for a Loss of Flow Event

Abstract

The purpose of this paper is to describe the methodology and results of the design assist analysis done to further optimize the reactor endshield configuration. Due to neutron and gamma radiation absorption and through conductiont convection and radiation from the primary coolant a considerable amount of heat is deposited within the endshield of the CANDU-3 reactor. During normal operating conditions this heat is removed by the endshield cooling system, which is based on forced circulation of water. In the event of a loss of endshield coolant flow the temperature of the water and the endshield structure rise, creating thermal gradients which in turn generate thermal stresses in the structure. Thermalhydraulic and thermal analysis codes are used to predict the effects of this loss of flow event.