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.
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
History of the ASME Code
Publications – Heat Exchangers, Pressure Vessels, Welds and Other Applications, Fatigue, Elevated Temperature
Links to Engineering Resources

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