This study concerns the cooling capacity of a high-temperature vertical pipe by a two-phase flow of superheated steam and droplets under Loss of Coolant Accident (LOCA) conditions. In order to characterize the cooling capacity, an experimental setup was developed. The heat flux removed from the wall during the cooling phase is investigated with the use of infrared thermography (IRT) while, simultaneously, the droplet diameter and velocity are characterized by a Phase Doppler system. In parallel, measurements of Laser Induced Fluorescence (LIF) are performed to obtain the mean droplet temperature. The present paper regards the influence of the inlet steam flow rate for a representative non-deformed nuclear core geometry at sub-channel scale. In general, rewetting occurs from bottom to top in the tube, starting early with the increase in the steam flow rate. As expected, during the Leidenfrost regime, the heat transfer is enhanced when increasing the steam flow rate. Finally, smaller droplets have higher velocities and the droplets temperature does not increase significantly from up-to downstream.