Comprehensive Prediction of Thermosyphon Characteristics in Reactor Passive Cooling System Simulation Loop FASSIP-01

Passive cooling mechanism for a nuclear reactor has been proven to be very important since the Fukushima Daiichi Reactor accident that was caused by active cooling system malfunction due to total loss of electrical power source. In the Center for Nuclear Reactor Technology and Safety of BATAN, the cooling mechanism was studied by using a natural circulation test loop named FASSIP-01 that applie d thermosyphon mechanism of water inside pipe s of 1” diameter . This study aimed to analytica l ly predict the thermal characteristics of the loop including its response time to wards steady condition using the MATLAB calculation program. This prediction derived the influence of several parameters such as the heat transfer coefficient of the cool er side (h-cooler) , the heater power, the elevation difference between the h eater and co o l er ( D Z ) , and the effects of the insulation thickness of pipe (IT) on the flowrate, temperature, and the heat power distribution across all components in the loop. The result show ed that by avoiding boiling condition , for transferring the heater power of 1 000 W and 2000 W, the needed h-cooler exceeds 200 and 400 W m - 2 ° C -1 , respectively. For a h-cooler of 200 W m - 2 ° C -1 , t he circulation flow rate increase d from 0.04 to 0.06 kg/s -1 for heater power increase from 1000 W to 2000 W. Those flow rates were d ecrease d to 0.037 and 0.052 kg s -1 by increasing h-cooler to 1000 W m - 2 ° C -1 . T he results we re in agreement with other studies on rectangular loops in the literature. T he time needed to reach 95 % towards steady state was predicted to be more than 13 hours. Reduction of this time to less than five hours was possible by reducing the heater tank volume from 100 L to 30 L or by modifying the starting heater input power.