Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development

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 fabricated for the first time by a commercial fuel vendor and subsequently...

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Veröffentlicht in:Journal of nuclear engineering and radiation science 2024-07, Vol.10 (3)
Hauptverfasser: Schulthess, Jason L., Baird, Katelyn, Petersen, Philip, Salvato, Daniele, Ozaltun, Hakan, Hanson, William A., Ullum, Nicholas, Giglio, Jeffrey, Cole, James I.
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Sprache:eng
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Zusammenfassung: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 fabricated for the first time by a commercial fuel vendor and subsequently irradiated in a test reactor. This provides an opportunity to evaluate postirradiation 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 was found as fission density increases. The data produced was evaluated using both Weibull statistics and a modulus degradation model with recommendations provided.
ISSN:2332-8983
2332-8975
DOI:10.1115/1.4064779