OCE has developed elevated temperature design criteria which have become part of the ASME Boiler and Pressure Vessel (B&PV) Code for nuclear power plant components.
This work included development of methods for fatigue evaluation, ductile failure mode analysis, the inelastic behavior of complex components, and design for cyclic service at elevated temperature. Some of these methods use the results of purely elastic analyses to perform simplified inelastic analysis of structures in elevated temperature service. Design criteria for acceptance of cracks in structural components subjected to cyclic loading at elevated temperature were included.
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We have Developed Material Design Criteria for Stainless Steel, Titanium and Nickel Alloys. Our Work also includes Performing Engineering Analysis on Elevated Temperature Equipment.
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Related Projects
– Development of Structural Evaluation Criteria for Elbows
– Development of Structural Evaluation Criteria for Bellows
– Engineering Analysis on Components in U.S. Submarines
Similar Services
– Elevated Temperature Design & Analysis
– Nuclear Power Plant Consulting
Resources
– Design Criteria of ASME Section III Subsection NH and for Very High Temperatures
– Background of the ASME Code
– Introduction to Fatigue Analysis
– Publications – Heat Exchangers, Pressure Vessels, Welds, Fatigue, Elevated Temperature
