Study on Thermohydraulic Characteristics of Pebble Bed Water Cooled Reactor Core

Study on the thermohydraulic characteristics of the pebble bed water cooled reactor (PBWR). The physical and geometrical model of the PBWR were built in which the thermal-hydraulic characteristics of the coolant were studied based on the computational fluid dynamics (CFD), meanwhile, STAP and TSAP code were established using Fortran 90. The results show that the surface temperature of the fuel element is much less than the design limit of 1 600 ℃, the maximum temperature on the surface of fuel element appears near the narrow gap area and the maximum velocity of the fuel element appears in the neutral position of the four narrow gap regions.