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RISAssessment of Candidate Fuel Cladding Alloys for the Canadian Supercritical Water Cooled Reactor Concept
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Selecting and qualifying a fuel cladding material for the Canadian supercritical watercooled reactor (SCWR) concept remains the most significant materials challenge to be overcome. The peak cladding temperature in the ...
Irradiation Issues and Material Selection for Canadian SCWR Components
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The Canadian super critical water-cooled reactor (SCWR) concept requires materials to operate at higher temperatures than current generation III water-cooled reactors. Materials performance after radiation damage is an ...
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 ...
Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr , Ni–Cr , and Fe–Cr Based Alloys
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Investigation of the role of irradiation on the corrosion resistance of structural alloys is of vital importance for selection of supercritical watercooled reactor (SCWR) materials. Gamma heating under SCWR conditions, ...
Steady State Radiolysis of Supercritical Water: Model Predictions and Validation
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Chemical kinetic models are being developed for the خ³radiolysis of subcritical and supercritical water (SCW) to estimate the concentrations of radiolytically produced oxidants. Many of the physical properties of water ...