Improvement of the Post-Critical Heat Flux (Chf) Heat Transfer Model used in the Korsar Thermohydraulic Computer Complex

A comparison has been presented of the results of calculating the temperature of the wall and steam with the empirical data of experiments modeling repeated impoundment of the core of water-cooled reactors. The need has been shown to improve the model implemented in the KORSAR computer complex for the case of low mass velocities and pressures. An engineering procedure has been proposed to account for droplets in removing heat in the region above the wetting front.