An analysis of the results of validation of thermohydraulic codes for an accident with depressurization of the main circulation circuit of the nuclear reactor of the WWER type

摘要

The analysis of outcomes of the heathydraulic codes validation with experimental data that were obtained on the integrated RMK stand simulating an accident with the depressurization of the reactor circuit is adduced in the paper. Are determined priority of application heathydraulic of codes for the analysis of failures with depressurization location of installations VVER.