United States Nuclear Regulatory Commission - Protecting People and the Environment

A Generalized Procedure for Generating Flaw-Related Inputs for the FAVOR Code (NUREG/CR-6817)

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Publication Information

Manuscript Completed: April 2003
Date Published: March 2004

Prepared by:
F.A. Simonen, S.R. Doctor,
G.J. Schuster, P.G. Heasler

Pacific Northwest National Laboratory
P.O. Box 999
Richland, WA 99352

D.A. Jackson, NRC Project Manager

NRC Job Code Y6604

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

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The U.S. Nuclear Regulatory Commission (NRC) has supported research to re-evaluate regulations for pressurized thermal shock. In addition to a severe overcooling transient and an embrittled material, a factor critical to reactor pressure vessel (RPV) failure is a crack-like flaw near the inner vessel surface. This report documents research on fabrication flaws performed at Pacific Northwest National Laboratory as part of a larger multiyear program sponsored by the NRC to address issues related to the reliability of ultrasonic testing and the development of improved programs for inservice inspection. These studies have generated data on flaws in RPVs in terms of flaw densities, flaw locations, and flaw sizes (through-wall depth dimensions and lengths). This report describes data from these studies, results from an expert judgment elicitation on RPV fabrication practices, and probabilistic models that characterize flaws that may exist in RPVs. A procedure is described for generating flaw-related parameters for use as inputs to probabilistic fracture mechanics calculations.

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