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    The Effect of Prior Cold Work on Tensile Residual Stress Development in Nuclear Weldments 

    Source: Journal of Pressure Vessel Technology:;2002:;volume( 124 ):;issue: 003:;page 359
    Author(s): Douglas J. Hornbach; Paul S. Prevéy
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Austenitic alloy weldments in nuclear reactor systems are susceptible to stress corrosion cracking (SCC) failures. SCC has been observed for decades and continues to be a primary maintenance ...
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