Publication | Closed Access

Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water reactor (PWR) and boiling-water reactor (BWR) ZIRCALOY cladding tubes: Part III. Mechanical behavior of hydride in stress-relieved annealed and recrystallized ZIRCALOYs at 20 °C and 300 °C

Materials ScienceEngineeringHigh Temperature MaterialsMechanical EngineeringHydrogen EmbrittlementHydride EmbrittlementIrradiation EffectsPressurized Water ReactorThermomechanical ProcessingMechanics Of MaterialsStructural Materials