Experimental validation of a modified RELAP5 model for transient analysis of Tehran research reactor mixed-core during fuel irradiation experiments

Hydraulic parameters, i.e., change of pool and hold-up tank water levels and coolant flow rate through the core as well as thermal parameters like clad and coolant temperature changes and also core power changes are desired parameters to be benchmarked using postulated transients. Good compatibility of experimental data and those predicted by modified RELAP5 model reveals the validity and accuracy of the model to be used for transient analysis in TRR mixed-core during irradiation experiments.