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    Development and Application of an LWR Reactor Pressure Vessel-Specific Flaw Distribution

    Published: 01 January 1994

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    Previous efforts by the U.S. Department of Energy have shown that the PWR reactor vessel integrity predictions performed through probabilistic fracture mechanics analysis for a pressurized thermal shock event are significantly sensitive to the overall flaw distribution input. It has also been shown that modern vessel in-service inspection (ISI) results can be used for development of vessel flaw distribution(s) that are more representative of U.S. vessels. This paper describes the development and application of a methodology to analyze ISI data for the purpose of flaw distribution determination. The resultant methodology considers detection reliability, flaw sizing accuracy, and flaw detection threshold in its application. Application of the methodology was then demonstrated using four recently acquired U.S. PWR vessel inspection data sets. The methodology helped provide original insight into several key inspection performance and vessel integrity prediction practice issues that will impact future vessel integrity evaluation. This paper briefly discusses the development and application of the methodology and the impact to future vessel integrity analyses.


    Reactor Vessel Integrity, Flaw Distribution, Pressurized Thermal Shock, Ultrasonic Inspection, Fracture Mechanics

    Author Information:

    Rosinski, ST
    Senior Member of Technical Staff, Sandia National Laboratories, Albuquerque, NM

    Kennedy, EL
    Staff Engineers, Failure Analysis Associates, Menlo Park, CA

    Foulds, JR
    Staff Engineers, Failure Analysis Associates, Menlo Park, CA

    Committee/Subcommittee: E10.02

    DOI: 10.1520/STP23939S