Substantiation and verification of the model for burnout in rod bundles of the KORSAR thermohydraulic code

Results of verification of a model for predicting burnout in uniformly heated rod bundles implemented in the improved KORSAR computer code are presented. In this code, the model for calculating the critical heat flux is based on the tabular method of FEI. In the process of verification, the predictions are compared with data taken from the experimental data bank of the Branch Base Center of Thermophysical Data (OBTsTD) of the FEI. These data are for rod bundles that are similar in design to the fuel assemblies of VVER reactors, and were obtained in a wide range of operating conditions: at pressures from 0.11 to 20 MPa and flow rates from 50 to 5000 kg/(m 2 s).