Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions
Kenneth Kane, Soon Lee, Samuel Bell, Nicholas R. Brown, Bruce A. Pint
Topics & Concepts
Cladding (metalworking)Zirconium alloyMaterials scienceBoiling water reactorBoilingLight-water reactorTemperature cyclingNuclear engineeringPressurized water reactorNuclear reactorComposite materialAlloyThermalChemistryThermodynamicsEngineeringOrganic chemistryPhysicsNuclear Materials and PropertiesNuclear reactor physics and engineeringFusion materials and technologies