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    Flaw Evaluation Procedure for Cast Austenitic Stainless-Steel Materials Using a Newly Developed Statistical Thermal Aging Model 

    Source: Journal of Pressure Vessel Technology:;2021:;volume( 143 ):;issue: 005:;page 051504-1
    Author(s): Uddin, Mohammed; Sallaberry, Cédric; Wilkowski, Gery
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Thermal embrittlement of some cast austenitic stainless steels (CASS) occurs at reactor operating temperatures leading to very low fracture toughness. Because of their low aged toughness with high variability, flaw evaluations ...
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    The Huge Missing Factor in Leak-Before-Break Analysis: How a Circumferential Through-Wall-Crack in a Pipe System Changes the Flexibility and Reduces the Applied Moments 

    Source: Journal of Pressure Vessel Technology:;2022:;volume( 144 ):;issue: 003:;page 31306-1
    Author(s): Uddin, Mohammed; Wilkowski, Gery; Kalyanam, Suresh; Brust, Fedrick
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In typical leak-before-break (LBB) analyses in the nuclear industry, the uncracked piping normal operating forces and moments are applied in a cracked-pipe analytical procedure to determine normal leakage, and the combined ...
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    Assessing the Secondary Stress in a Pipe System With Circumferential Surface Crack Using Finite Element Modeling 

    Source: Journal of Pressure Vessel Technology:;2022:;volume( 144 ):;issue: 005:;page 51802-1
    Author(s): Uddin, Mohammed; Kalyanam, Sureshkumar; Wilkowski, Gery; Brust, Frederick; Martin, John
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In flaw evaluation criteria, the design limits for the secondary stresses are frequently different than the primary stresses. The evaluation procedure for primary stresses is load-controlled based which is independent of ...
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    Welding Residual Stress in a Large Diameter Nuclear Reactor Pressure Vessel Nozzle 

    Source: Journal of Pressure Vessel Technology:;2013:;volume( 135 ):;issue: 002:;page 21208
    Author(s): Zhang, Tao; Brust, Frederick W.; Wilkowski, Gery; Xu, Heqin; Betervide, Alfredo A.; Mazzantini, Oscar
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The Atucha II nuclear power plant is a pressurized heavy water reactor (PHWR) being constructed in Argentina. The original plant was designed by Kraftwerk Union (KWU) in the 1970’s using the German methodology of break ...
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    Leak Before Break Under Beyond Design Basis Seismic Loading 

    Source: Journal of Pressure Vessel Technology:;2013:;volume( 135 ):;issue: 005:;page 51801
    Author(s): Zhang, Tao; Brust, Frederick W.; Wilkowski, Gery; Xu, Heqin; Betervide, Alfredo A.; Mazzantini, Oscar
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The Atucha II nuclear power plant is a unique pressurized heavy water reactor (PHWR) being constructed in Argentina. The original plant design was by Kraftwerk Union (KWU) in the 1970's using the German methodology of break ...
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