Thermal hydraulic analysis of the Bandung Triga 2000 research reactor.

With regard to safe operation of the TRIGA 2000 reactor at a power of 1000 kW, the thermal hydraulic analysis has been carried out by using code STAT. The analysis has been focused on the calculation of the maximum powered fuel element (hottest cannel) concerning to heat flux of fuel elements, coolant velocities and coolant temperature. In addition, safety margin to critical heat flux wasalso determined. For the current core condition (111 fuel elements in the core) and for the water inlet temperature of 32 ° C (design inlet water temperature), the maximum flow velocity is 28.9 cm/s for the maximum powered fuel element. These results correspond to the exit coolant channel temperature of 58.77 °C. [ABSTRACT FROM AUTHOR]