Mechanical Properties of DU-xMo Alloys with x = 7 to 12 Weight Percent
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Abstract
Mechanical properties of six depleted uranium-molybdenum (U-Mo) alloys have been obtained using microhardness, quasistatic tensile tests, and scanning electron microscopy (SEM) failure analysis. U-Mo alloy foils are currently under investigation for potential conversion of high power research reactors to low enriched uranium fuel. Although mechanical properties take on a secondary effect during irradiation, an understanding of the alloy behavior during fabrication and the effects of irradiation on the integrity of the fuel is essential. In general, the microhardness, yield strength, Young’s modulus, and ultimate tensile strength improved with increasing Mo content. Microhardness measurements were very sensitive to local composition, while the failure mode was significantly controlled by the impurity concentration of the alloy, especially carbon. Values obtained from literature are also provided with reasonable agreement, even though processing conditions and applications were quite different in some instances.
Keywords
Uranium Ultimate Tensile Strength Homogenization Treatment Molybdenum Content Dispersion FuelNotes
Acknowledgments
Work supported by the United States Department of Energy, Office of the National Nuclear Security Administration (NNSA), under DOE Idaho Operations Office (Contract No. DE-AC07-05ID14517). The authors are especially grateful to the Fuels and Applied Sciences Building (FASB) and Electron Microscopy Laboratory (EML) staff. The authors specifically acknowledge Dr. Thomas Hartmann, Mr. Glenn Moore, Mr. Michael Chapple, Mr. Steven Steffler, Mr. Blair Park, Mrs. Terri Dixon, and Ms. Kristine Baker for their assistance with fabrication, sample preparation, and material transfers related to these experiments. Finally, the authors acknowledge the Health and Physics staff for their continued support of this work in the FASB and EML facilities.
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