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

Materials ScienceHigh Temperature MaterialsEngineeringMechanical EngineeringHydrogen EmbrittlementHydride EmbrittlementIrradiation EffectsPressurized Water ReactorThermomechanical ProcessingMechanics Of MaterialsStructural Materials