Knowledge regarding the rewetting phenomenon is of high interest in Light Water Reactors as this is associated with temperature gradients and thermal shock in the cladding surface, and the peak cladding temperature. These parameters are critical in the assessment of the fuel pin after an accident as they are associated with possible failures due to fatigue and oxidation of the surface, especially if the cladding is composed of zirconium. In this case, oxidation takes place if the peak cladding temperature reaches values above 850°C, generating hydrogen and damaging the cladding due to an exothermic reaction. The present paper provides state-of-the-art high-spatial and high-temporal resolution cladding temperature data obtained through Fiber-Optic Distributed Temperature Sensors during departure from nucleate boiling events under prototypical Light Water Reactor conditions of temperature, pressure, rod diameter, and heat flux profile (cosine shape). The test section had a total heated length of 2 m. Results were obtained for a bare and a chromium coated (i.e., accident tolerant fuel material) zircaloy at a mass velocity of 2712 kg/m²s, pressures from 10 MPa to 20 MPa and subcooling of 10°C to 55°C. Three optical fibers were azimuthally placed inside the simulated fuel pins to provide a circumferential assessment of the dryout and rewetting phenomenon. The resolution of these temperature measurements was 2.5 mm axially and they were obtained at a frequency of 100 Hz. Peak cladding temperature and rewetting times were extracted from the temperature data. Higher peak temperatures were in general observed for the bare zircaloy compared to the chromium-coated simulated fuel pin, reaching temperatures up to 1100°C. The rewetting time was also found proportional to the peak cladding temperature.