Critical heat flux in saturated and subcooled boiling for R-113 jet impingement on the stagnation zone

An experimental investigation was carried out to measure the critical heat flux (CHF) of steady saturated and subcooled boiling for a round R-113 jet impingement on the flat stagnation zone. The experimental data were measured in a steady nucleate boiling state. Three main influencing parameters, i.e., subcooling, impact velocity and jet nozzle diameter were varied over a wide range and their effects on the critical heat flux were systemically studied. Two empirical correlations were respectively obtained using the experimental data for predicting the critical heat flux of R-113 jet impingement on the flat stagnation zone.