Thermal hydraulic simulation of the triga ipr-r1 research reactor

Abstract

The safety analysis of research reactors includes simulations of selected cases classified by the International Atomic Energy Agency (IAEA), since the simulations are performed using validated nodalizations and internationally recognized, accepted and validated best estimate codes. The thermal-hydraulic analysis is considered as an essential aspect in the study of safety of nuclear reactors, since it can predict proper working conditions, steady-state and transient, thereby ensuring the safe operation of a nuclear reactor. A RELAP5 model verified for the IPR-R1 TRIGA research reactor was used here to study. A loss of coolant accident (LOCA) event was simulated. The obtained results demonstrate that it is necessary to consider also the neutronic feedback effects in the thermal hydraulic calculations to more realistically simulate this type of incident as it is shown in this work.