Simulations of loss-of-coolant accidents for containments of the second and the third PWR generation

The work deals with modeling of thermal-hydraulic processes taking place within a containment of a pressurized water reactor (PWR) during the Loss-of-Coolant Accident - LOCA. Aim of the work is to compare thermodynamic consequences of the LOCA within containments of pressurized water reactors of the second and the third generation types. Simulations have been conducted for the two-loop Westinghouse PWR and for design data of the AP-600 reactor. Calculations have been realized using a computer code HEPCAL-AU worked out at the Institute of Thermal Technology of the Silesian University of Technology, and using the PWR reactor simulator made by the Cassiopeia Technologies. A set of multi-variant simulations for different accident scenarios have been accomplished. Based on the obtained results the analysis of the effectiveness of functioning of the considered systems has been done. The selected results of calculations and the most important conclusions are presented in the paper.