Overview of fatigue crack initiation in carbon and low-alloy steels in light water reactor environments

Journal Article · Mon Feb 01 04:00:00 EST 1999 · Journal of Pressure Vessel Technology

DOI:https://doi.org/10.1115/1.2883667· OSTI ID:328399

Chopra, O K; Shack, W J ^[1]

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1. Argonne National Lab., IL (United States). Energy Technology Div.

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 {micro}m 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.

• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States); USDOE, Washington, DC (United States)
• OSTI ID: 328399
• Journal Information: Journal of Pressure Vessel Technology, Journal Name: Journal of Pressure Vessel Technology Journal Issue: 1 Vol. 121; ISSN 0094-9930; ISSN JPVTAS
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
CARBON STEELS
CORROSION FATIGUE
CRACK PROPAGATION
LOW ALLOY STEELS
SERVICE LIFE
WATER CHEMISTRY
WATER COOLED REACTORS