Stress Intensity Factor Influence Coefficients for Semi-Elliptical Axial Surface Flaws for Cylindrical Components With Large Thickness to Radius Ratios
Abstract:Flaws detected in nuclear power plant components during in-service inspections are typically evaluated based on stress intensity factor influence coefficient databases and solutions from industry standards and public literature (e.g. API-579, ASME Section XI Code, WRC-175 Bulletin, Raju-Newman, etc). For certain components in the Pressurized Water Reactor (PWR) nuclear power plants, such as Bottom Mounted Instrumentation (BMI) nozzles, the cylindrical component geometry may fall outside the applicability limit… Show more
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