The ROSA-IV program is conducting integral experiments for investigation of thermal-hydraulic responses of a pressurized water reactor (PWR) during small-break loss-of-coolant accidents (SBLOCA) and operational transients using the Large Scale Test Facility (LSTF) which is a 1/48 volumetrical scaled, full-height, full-pressure simulator of a westinghouse-type 4-loop PWR. During a LOCA, the reactor coolant system, may become steam-water two-phase flow conditions with a predominant influence of gravity on the spatial distribution of reactor coolant. The LSTF experiments simulate such two-phase flow behavior and measure thermal-hydraulic responses by using more than 2300 transducers. A motion-picture graphic display processor has been developed to allow efficient interpretation of the measured data. The processor generates a color motion picture from both experimental and RELAP5-calculational results to be used for the presentation of the system transient responses. (author).