LIQUID FILM BEHAVIOUR IN ANNULAR DISPERSED FLOW AT CRITICAL HEAT FLUX
Liquid film flow rates and critical heat fluxes were measured in a concentric, internally heated annulus with steam-water upflow at pressures and velocities of interest in nuclear reactors. At the boiling crisis the film
broke down locally at the heater top but an appreciable film continued to flow around the dry patch onto an unheated deposition section. This residual flow was allowed to grow by droplet deposition over pre-determined
lengths before being removed through a porous wall. From the growth rate of the new films, deposition fluxes were obtained, and an equation for the entrainment flux is proposed.