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RISLow Cycle Fatigue and Creep Fatigue Behavior of Alloy 617 at High Temperature
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Alloy 617 is the leading candidate material for an intermediate heat exchanger (IHX) application of the very high temperature nuclear reactor (VHTR), expected to have an outlet temperature as high as 950 آ°C. Acceptance ...
A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors
Publisher: American Society of Mechanical Engineers (ASME)
Abstract: The low-pressure depressurization system (LPDS) of advanced passive pressurized water reactors (PWRs) is designed to provide depressurization of the reactor coolant system during a small break loss-of-coolant accident ...