Critical heat flux on zircaloy and accident tolerant fuel cladding under prototypical conditions of pressurized and boiling water reactors
Tiago Augusto Moreira, DongHwi Lee, Mark Anderson
Topics & Concepts
Cladding (metalworking)SubcoolingMaterials scienceBoilingNucleate boilingCritical heat fluxHeat fluxWettingComposite materialLight-water reactorZirconium alloyLoss-of-coolant accidentCoolantMechanicsThermodynamicsNuclear engineeringHeat transferEngineeringPhysicsAlloyNuclear Materials and PropertiesNuclear reactor physics and engineeringNuclear Engineering Thermal-Hydraulics