Recent test data illustrate potentially significant effects of light water reactor (LWR) coolant environments on the fatigue resistance of carbon and low-alloy steels. The crack initiation and crack growth characteristics of carbon and low-alloy steels in LWR environments are presented. Decreases in fatigue lives of these steels in high-dissolved-oxygen water are caused primarily by the effect of environment on growth of short cracks <100 μm in depth. The material and loading parameters that influence fatigue life in LWR environments are defined. Statistical models have been developed to estimate the fatigue lives of these steels in LWR environments, and design fatigue curves have been developed for carbon and low-alloy steel components in LWR environments. The significance of environmental effect on the current Code design curve is evaluated.
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February 1999
Review Articles
Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments
O. K. Chopra,
O. K. Chopra
Energy Technology Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
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W. J. Shack
W. J. Shack
Energy Technology Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
Search for other works by this author on:
O. K. Chopra
Energy Technology Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
W. J. Shack
Energy Technology Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439
J. Pressure Vessel Technol. Feb 1999, 121(1): 49-60 (12 pages)
Published Online: February 1, 1999
Article history
Received:
May 21, 1998
Revised:
July 21, 1998
Online:
February 11, 2008
Citation
Chopra, O. K., and Shack, W. J. (February 1, 1999). "Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments." ASME. J. Pressure Vessel Technol. February 1999; 121(1): 49–60. https://doi.org/10.1115/1.2883667
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