United States Nuclear Regulatory Commission - Protecting People and the Environment

Tensile-Property Characterization of Thermally Aged Cast Stainless Steels (NUREG/CR-6142, ANL-93/35)

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Publication Information

Manuscript Completed: January 1994
Date Published:
February 1994

Prepared by:
W.F. Michaud, P.T. Toben, W.K. Soppet, O.K. Chopra

Argonne National Laboratory
9700 South Cass Avenue
Argonne, Illinois 60439

Prepared for:
Division of Engineering
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

NRC FIN A2243

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Abstract

The effect of thermal aging on tensile properties of cast stainless steels during service in light water reactors has been evaluated. Tensile data for several experimental and commercial heats of cast stainless steels are presented. Thermal aging increases the tensile strength of these steels. The high-C Mo-bearing CF-8M steels are more susceptible to thermal aging than the Mo-free CF-3 or CF-8 steels. A procedure and correlations are presented for predicting the change in tensile flow and yield stresses and engineering stress-vs.-strain curve of cast stainless steel as a function of time and temperature of service. The tensile properties of aged cast stainless steel are estimated from known material information, i.e., chemical composition and the initial tensile strength of the steel. The correlations described in this report may be used for assessing thermal embrittlement of cast stainless steel components.

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