David Lávička

Investigation of Thermal-Hydraulic Field in the Annular Channel Around the Heated Wall of the Fuel Rod

Experimental measurement serves for investigation of temperature field in the annular flow channel along the heated wall of the fuel rod. Research focuses on the issue of heat transfer into the coolant at two-phase turbulent flow. Two-phase turbulent flow contains a large quantity of bubbles and, with heat transfer; it represents a very complex process. The annular flow depends on the application of spacers that affect the flow and temperature field in the flow channel at the fuel rod model. The fuel rod represents the fuel cluster in nuclear pressurized water reactor (PWR) of the VVER type.Copyright