[en] The results from Power-Cooling-Mismatch Test PCM-3 are presented. The primary objective of the test was to determine the behavior of previously unirradiated pressurized water reactor (PWR) fuel rods operated under sustained film boiling conditions with cladding temperatures in the alpha plus beta temperature range (1105 to 1245 K). Information was also obtained on the thermal-hydraulic conditions affecting the onset, propagation, and termination of departure from nucleate boiling (DNB). Four PWR-type fuel rods were subjected to five DNB cycles in a PWR environment in the in-pile test loop of the Power Burst Facility. Departure from nucleate boiling was induced by reducing coolant flow while maintaining a constant rod peak power of about 54 kW/m. The first four DNB cycles were short, whereas film boiling operation lasted for up to 45 seconds during the fifth cycle. Cladding temperatures for two rods stabilized in the alpha-phase temperature range (810 to 1105 K), and the cladding temperatures of the other two rods reached the beta-phase temperature range