EVALUATION OF THERMAL CONDUCTION BETWEEN TWO SUBCHANNELS WITH A COMPUTATIONAL FLUID DYNAMICS CODE

摘要

An accurate thermal conduction model is required to develop a detailed threedimensional thermal-hydraulics model for the application to liquid metal-cooled reactors. We generate the data of conduction correction factor for the liquid sodium through the CFX calculations. The correction factor is defined as the ratio of the local conduction heat flux to the average heat flux. The dependency of the data on Re is very weak and they are nearly constant for the given geometry and temperature difference. The data are useful for the development of a general thermal conduction model applicable to the existing sub-channel codes. The correction factor between 1.6 and 1.7 is recommended for a sodium-cooled reactor.