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RISGeneral Corrosion of Chromium-Coated Zirconium- and Titanium-Based Alloys in Supercritical Water at 500 °C
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The 300 MWel small Canadian supercritical water-cooled reactor (SCWR), which is a scaled-down version of the original 1200 MWel concept, has a smaller core, uses low enriched uranium fuel instead of a plutonium–thorium ...
Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Canadian Nuclear Laboratories has an on-going Research &
Fission Product Release Under Supercritical Water Cooled Reactor Conditions
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Most supercritical watercooled reactor (SCWR) concepts being considered as part of the Generation IV initiative are direct cycle. In the event of a fuel defect, the coolant will contact the fuel pellet, potentially releasing ...