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Application of Corrosion Fatigue Crack Growth Rate Data to Integrity Analyses of Nuclear Reactor Vessels
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The methodology of fatigue crack growth analysis in evaluating structural integrity of nuclear components has been well established over the years, even to the point where a recommended practice ...
Fatigue Crack Growth of Stainless Steel Piping in a Pressurized Water Reactor Environment
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Fatigue crack-growth behavior was investigated for types 304 and 316 stainless steel exposed to a pressurized water reactor environment. The effects of test frequency, stress ratio, specimen ...
Technical Basis for Revised Reference Crack Growth Rate Curves for Pressure Boundary Steels in LWR Environment
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Reference fatigue crack growth rate curves have been contained in Appendix A of Section XI since its inception. The curves have been designed to be applicable to carbon and low alloy pressure ...
Reactor Coolant Pump Flywheel Overspeed Evaluation
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The overspeed capability of the large steel flywheels used on light water reactor primary coolant pumps has been evaluated through a combined analytical and experimental effort. Limiting speeds ...
Thermal Aging of Cast Stainless Steel, and Its Impact on Piping Integrity
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A series of experiments were conducted to characterize the effects of high temperature service (550–650°F or 288–343°C) on the mechanical properties of cast stainless steels. The material ...