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RISThermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Performance of two distinct fuel systems, U-7Mo fuel in Zircaloy (Zry-4) cladding and U-10Mo fuel in aluminum (Al6061-O) cladding was studied. First, a mini plate with Zry-4 cladding from a previous irradiation experiment ...
Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A plate-type nuclear fuel consisting of a solid monolithic foil of U-10 wt. %Mo is under development for use in the United States' high-performance research reactors. In support of developing this fuel, the fuel has been ...