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RISQuantitative Estimation of the Growth of Environmentally Assisted Cracks at Flaws in Light Water Reactor Components
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Since environmentally assisted cracking (EAC) is an important degradation mechanism affecting the structural materials of nuclear power plants, numerous EAC experiments have been performed in the ...
A New Parameter for Characterizing Corrosion Fatigue Crack Growth
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The role of mechanical factors, such as ΔK, R, and K̇ (loading rate), and its significance on corrosion fatigue crack growth acceleration were discussed in terms of crack tip strain rate ...
Evaluation of Radiation Damage in Reactor Pressure Vessel Steel by Elastic-Plastic Fracture Mechanics
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Elastic-plastic toughness characterization of SA533B nuclear pressure vessel steel is described in terms of the J integral approach. A simple test procedure has been proposed from which the JIC ...