CorTAF: A nuclear reactor core three-dimensional thermal-hydraulic characteristics analysis code based on OpenFOAM
Kai Liu, Mingjun Wang, Wenxi Tian, Jing Zhang, Suizheng Qiu, G.H. Su
Topics & Concepts
Thermal hydraulicsHeat transferBundleNuclear engineeringCoolantThermal conductionNuclear reactor corePressurized water reactorNuclear reactorComputational fluid dynamicsDecay heatTransient (computer programming)MechanicsMaterials scienceMechanical engineeringEngineeringComputer sciencePhysicsOperating systemComposite materialNuclear Engineering Thermal-HydraulicsNuclear reactor physics and engineeringHeat transfer and supercritical fluids