Theoretical and experimental investigation of the thermal–hydraulic parameters of the Bandung TRIGA research reactor

Abstract

Safe and optimum operation of the Bandung TRIGA research reactor, theoretical and the experimental study of its thermal–hydraulic parameters have been conducted. Investigations have been focused on a maximum powered channel concerning to coolant temperature, void fraction, heat flux and coolant velocities. Results of theoretical investigations, the core condition and water inlet temperature of 28 °C, the maximum flow velocity is 34.0 and 26.4 cm/s for the thermal power 2000 kW and 1000 kW. These results correspond to the exit coolant channel temperature of 70.3 and 55.0 °C, respectively. The experimental investigations indicated that exit coolant temperature in maximum powered channel for the thermal power of 1000 kW is almost the same as exit coolant temperature for the thermal power of 2000 kW as result of theoretical investigations is 70 °C. All of these thermal–hydraulic parameters under normal operation condition are the safety criteria of the research reactor.