Characterization of Flaws in U.S. Reactor Pressure Vessels: Validation of Flaw Density and Distribution in the Weld Metal of the PVRUF Vessel (NUREG/CR-6471, Volume 2)
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Manuscript Completed: June 2000
Date Published: August 2000
G. J. Schuster, S. R. Doctor, A.F. Pardini, S.L. Crawford
Pacific Northwest National Laboratory
Richland, WA 99352
D.A. Jackson, NRC Project Manager
Division of Systems Analysis and Regulatory Effectiveness
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC Job Code L1099 and W6275
Characterization of Flaws in U.S. Reactor Pressure Vessels is a multi-volume report. Volume 2, this document, contains the results of a destructive analysis for fabrication flaws in weld metal removed from the Pressure Vessel Research User Facility (PVRUF) vessel. Confirmed flaw rates are estimated, and a comparison is made to the Marshall distribution. The first volume of this multi-volume report gives the density and distribution of flaw indications recorded from the volumetric ultrasonic inspections of the vessel made through the cladding. Volume 3 reports the distribution of flaw indications in material removed from a BWR vessel, the Shoreham vessel.
This volume provides a description of research methods developed at Pacific Northwest National Laboratory for confirming flaw rates in weld metal. The data, acquired during the research, are shown with the estimates of flaw density as a function of through-wall size. Because the largest flaws were found in repair weld metal, the report contains the size and number of repairs to the PVRUF vessel.