RT Journal Article ID 1cfb457f4174d6f6 A1 Reis, Patricia Amélia de Lima A1 Lombardi Costa, Antonella A1 Pereira, Claubia A1 Veloso, Maria Auxiliadora Fortini A1 Miró, Rafael Herrero A1 Martin, Gumersindo Verdú T1 EVALUATION OF THE NEUTRONIC FEEDBACK EFFECTS IN LOSS OF COOLANT ACCIDENT SIMULATION OF THE IPR-R1 TRIGA REACTOR JF Computational Thermal Sciences: An International Journal JO CTS YR 2019 FD 2018-11-20 VO 11 IS 3 SP 243 OP 254 K1 nuclear research reactor K1 thermal hydraulic simulation K1 neutronic/thermal hydraulic couple calculation AB 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 perform transient studies. A loss of coolant accident (LOCA) event was simulated. The obtained results demonstrate that, to more realistically simulate this type of transient, it is necessary to consider also the neutronic feedback effects in the thermal hydraulic calculations. PB Begell House LK https://www.dl.begellhouse.com/journals/648192910890cd0e,6a05a6167690f470,1cfb457f4174d6f6.html