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    Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel 

    Source: Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 001:;page 11009
    Author(s): Sáez-Maderuelo, Alberto; Gómez-Briceño, Dolores; Maffiotte, César
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The supercritical water reactor (SCWR) is one of the Generation IV designs. The SCWR is characterized by its high efficiency, low waste production, and simple design. Despite the suitable properties of supercritical water ...
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    Microstructure Study of NiCrAlY and FeCrAlY Exposed to Superheated Steam at 800 °C 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 001:;page 11015
    Author(s): Sáez-Maderuelo, Alberto; McTaggart, Michael; Huang, Xiao; Maffiotte, César
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Supercritical water-cooled reactor (SCWR) was chosen as Generation IV reactor concept in Canada to utilize Canada's expertise and technical capabilities from past research and designs. The conceptual design of Canadian ...
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