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    Validation of Constant Load C-Ring Apex Stresses for Stress Corrosion Cracking Testing in Supercritical Water 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002:;page 21004
    Author(s): Swift, R.; Cook, W.; Bradley, C.; Newman, R.C.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In selecting the materials for the Canadian supercritical water-cooled reactor (SCWR), the effects and extent of stress corrosion cracking (SCC) on candidate alloys of construction, under various operational conditions, ...
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    Adhesion of Oxides Grown in Supercritical Water on Selected Austenitic and Ferritic/Martensitic Alloys 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 002:;page 21006
    Author(s): Artymowicz, D.; Bradley, C.; Xing, B.; Newman, R. C.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A series of austenitic alloys (800H, H214, I625, 310S, and 347) with different surface finishes were exposed to supercritical water (SCW) at 550 °C and 2.5 × 107 Pa for 120 h, 260 h, and 450 h in a static autoclave with ...
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