Jason Schulthess, Katelyn Baird, Philip Petersen, Daniele Salvato, Hakan Ozaltun, William Hanson, Nicholas Ullum, Jeffrey J. Giglio, James I. Cole
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Mechanical Properties of Irradiated U-10wt%Mo Alloy Degraded by Porosity Development
A plate-type nuclear fuel consisting of a solid monolithic foil of U-10wt%Mo is under development for use in the United States' high performance research reactors. In support of developing this fuel, the fuel has been fabricated for the first time by a commercial fuel vendor and subsequently irradiated in a test reactor. This provides an opportunity to evaluate post-irradiation mechanical properties of the commercially fabricated fuel. Four-point bend testing was conducted on the irradiated U-10Mo samples to generate the fuel material properties, including the modulus of elasticity and the bending strength. Although the material behaves in a brittle manner due to the accumulated porosity, a general trend of strength and modulus reduction were found as fission density increases. The data produced was evaluated using both Weibull statistics and a modulus degradation model with recommendations provided.
期刊介绍:
The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.