OCE 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.


We have developed material design criteria for stainless steel, titanium and nickel alloys. Our work also includes performing design and stress, vibration and fatigue analysis on 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


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, Weld Applications, Fatigue, Elevated Temperature

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