Safe and effective loading of nuclear reactor fuel assemblies demand qualitative and quantitaive analysis of the relations between the coolant temperature in the fuel assembly outlet, measured by a thermocouple, and the mean temperature of the coolant in the thermocouple plane position. In the laboratory at the Institute of Thermal Power Engineering of the Slovak University of Technology in Bratislava, an experiemental physical fuel assembly model of the VVER 440 nuclear power plant with V 213 nuclear reactors was installed The aim of the measurements on the physical model was to analyze the temperature and velocity profiles in the fuel assembly outlet. The following article deals with the analyses of these measurements based on different mass flow of the water through a physical model of the fuel assembly outlet. The following arficle deals with the analysis of these measurements based on different discontinuity generated by cold water flowing through triplet tubes and central tube in plane 1, and the positioning of the mixing CFD grid simulations of a fuel assembly outlet. All analyses were validated by means of measurements on the physical model of the fuel assembly. and Obsahuje seznam literatury