Search
CSV
RISCorrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels in PWR Primary Water
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Experimental results for corrosion fatigue crack growth in several different ferritic pressure vessel steels including A533-B and A508-III exposed to simulated PWR primary water at 288°C are ...
Development of Engineering Codes of Practice for Corrosion Fatigue
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The recognition that time-dependent effects of aqueous corrosion can have a large influence on fatigue failure in carbon and low alloy steels for nuclear reactor pressure vessels is having an ...
Errata: “Corrosion Fatique Crack Growth in Reactor Pressure Vessel Steels in PWR Primary Water” (Journal of Pressure Vessel Technology, 1983, 105, pp. 245–254) and “Development of Engineering Codes of Practice for Corrosion Fatigue” (Journal of Pressure Vessel Technology, 1983, 105, pp. 255–262)
Publisher: The American Society of Mechanical Engineers (ASME)