Leak-Before-Break Methodologies for Reactor Coolant Systems
Leak-before-break (LBB) approaches may be used to eliminate consideration of the dynamic effects of pipe rupture in reactor coolant piping systems, justifying removal or non-installation of pipe-whip restraints and jet impingement barriers. NRC LBB criteria require demonstrating a low probability of pipe rupture, then determining maximum critical flaw size via fracture mechanics, followed by thermal-hydraulic analysis to determine leakage for one half the critical size for normal plant operation, and demonstrating that there is adequate margin between predicted leakage and plant leakage detection capability. This informative SI Webinar discusses LBB methodology, NRC requirements, and current developments, as well as LBB evaluations performed by SI - and accepted by the NRC - at several plants.
Presented on: May 6, 2009
Instructor:
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About the Instructor
Art Deardorff, PE has a MS in Mechanical Engineering from the University of Arizona, and a BSME from Oregon State University. He has over 35 years of experience in design, analysis, testing, and failure assessment of structures, systems, and components. Deardorff's achievements include development of innovative approaches for assessing remaining life of nuclear and fossil power plant components, and participation in several industry programs to address thermal fatigue and leak-before-break for reactor coolant systems. He has taught ASME Code seminars worldwide.