Development of Engineering Codes of Practice for Corrosion Fatigue

[+] Author and Article Information
P. M. Scott

Materials Development Division, Harwell, Didcot, Oxon, Oxfordshire, England

B. Tomkins

Springfields Nuclear Power Development Laboratory, Salwick, Preston, England

A. J. E. Foreman

Metallurgy Division, Harwell, Didcot, Oxon, Oxfordshire, England

J. Pressure Vessel Technol 105(3), 255-262 (Aug 01, 1983) (8 pages) doi:10.1115/1.3264275 History: Received May 12, 1982; Revised March 30, 1983; Online November 05, 2009


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 important influence on the continuing process of revision and improvement of design and inspection codes. The contrasting requirements of engineering codes for design purposes or for in-service inspection purposes are discussed. The critical assumptions in each are highlighted and illustrated with examples incorporating recent improvements in the mechanistic understanding of the development of corrosion fatigue failure. The consequences of adopting a crack-tolerant approach in the design phase, as distinct from the evaluation of defects found in service, are also critically examined.

Copyright © 1983 by ASME
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