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    Overview of Fatigue Crack Initiation in Carbon and Low-Alloy Steels in Light Water Reactor Environments 

    Source: Journal of Pressure Vessel Technology:;1999:;volume( 121 ):;issue: 001:;page 49
    Author(s): O. K. Chopra; W. J. Shack
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Recent test data illustrate potentially significant effects of light water reactor (LWR) coolant environments on the fatigue resistance of carbon and low-alloy steels. The crack initiation and ...
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    A Review of the Effects of Coolant Environments on the Fatigue Life of LWR Structural Materials 

    Source: Journal of Pressure Vessel Technology:;2009:;volume( 131 ):;issue: 002:;page 21409
    Author(s): O. K. Chopra; W. J. Shack
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code specifies design curves for the fatigue life of structural materials in nuclear power plants. However, the ...
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    A Note on Peristaltic Pumping 

    Source: Journal of Applied Mechanics:;1974:;volume( 041 ):;issue: 002:;page 520
    Author(s): M. P. Negrin; W. J. Shack; T. J. Lardner
    Publisher: The American Society of Mechanical Engineers (ASME)
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    Stress Corrosion Crack Growth Rates in Type 304 Stainless Steel in Simulated BWR Environments 

    Source: Journal of Engineering Materials and Technology:;1986:;volume( 108 ):;issue: 001:;page 20
    Author(s): J. Y. Park; W. E. Ruther; T. F. Kassner; W. J. Shack
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Stress corrosion cracking of Type 304 stainless steel has been studied with fracture-mechanics-type standard 25.4-mm-thick compact tension specimens in simulated boiling-water reactor environments ...
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