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Effect of Flaw Characterization on the Structural Integrity Evaluation Under Pressurized Thermal Shock
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 Title & Authors
Effect of Flaw Characterization on the Structural Integrity Evaluation Under Pressurized Thermal Shock
Kim, Jin-Su; Choe, Jae-Bung; Kim, Yeong-Jin; Park, Yun-Won;
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The reactor pressure vessel is usually cladded with stainless steel to prevent corrosion and radiation embrittlement. Number of subclad cracks may be found during an in-service-inspection due to the presence of cladding. It is specified, in ASME Sec. XI, that a subclad crack is characterized as a surface crack when the thickness of the clad is less than 40% of the crack depth. This condition is provided to keep the crack integrity evaluation conservative. In order to refine the fracture assessment procedures for such subclad cracks under a pressurized thermal shock condition, three dimensional finite element analyses are applied for various subclad cracks existing under cladding. A total of 36 crack geometries are analyzed, and the results are compared with those for surface cracks. The resulting stress intensity factors for subclad cracks are 6 to 44% less than those for surface cracks. It is proven that the flaw characterization condition as specified in ASME Sec. XI can be overly conservative for some subclad cracks.
Reactor Pressure Vessel;Subclad Crack;Cladding;Surface Crack;Pressurized Thermal Shock;Stress Intensify Factor;
 Cited by
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