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Meeting Materials Science & Technology 2019
Symposium Materials for Nuclear Applications
Presentation Title P3-67: Investigation of Recrystallization and Grain Growth in Uranium 10 wt% Molybdenum
Author(s) Jacqueline I. Reeve, Vineet Joshi, David Field
On-Site Speaker (Planned) Jacqueline I. Reeve
Abstract Scope Uranium 10 wt% Molybdenum (U-10Mo) is being explored as a replacement for highly enriched uranium (HEU) fuels used in advanced research and test reactors. In this study, the texture and grain growth kinetics of depleted U-10Mo are analyzed. The U-10Mo microstructure and transitions that occur during recrystallization and grain growth are important due to their influence on the fuels performance and swelling kinetics in reactor operation. U-10Mo samples as hot rolled (80% total reduction) and as cold rolled (10%, 30%, and 50% total reduction) were annealed at 600˚C and 700˚C for time periods ranging from 1-8 hours. Electron Backscattered Diffraction (EBSD) was employed to observe and quantify recrystallization and grain growth in the samples. The effects of plastic deformation and annealing temperature control the nucleation and growth rates for recrystallization. Optimum conditions are identified to obtain specific grain size distributions.

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Combined Use of In-situ and Ex-situ TEM to Characterize Irradiation Induced Dislocation Loops in F/M Steels for Nuclear Applications
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Compatibility of U3Si2 fuel with FeCrAl and SiC/SiC Based Cladding
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Design of Alloy Chemistry to Mitigate Fuel-Cladding Chemical Interactions in Uranium-based Metallic Fuels
Development and Performance of High Temperature Irradiation Resistant Thermocouples
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Evolution of Microstructure, Deformation Mechanisms, and Internal Damage During Creep-Fatigue Testing of Alloy 709 (Fe-20Cr-25Ni)
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In-situ Characterization of Zirconium Alloy Degradation to Support Nuclear Sensing Applications
In-situ Ion Irradiation Study of Silicon Carbide-Carbon Coated Nanostructured Ferritic Alloy
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P3-67: Investigation of Recrystallization and Grain Growth in Uranium 10 wt% Molybdenum
P3-68: Oxidation of TRISO particles and Matrix Graphite in Mixed Gas Atmospheres
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Spectral Thermal Conductivity Predictions in UO2 with Xe Inclusions
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Thermophysical Properties of Binary Cl & F Compositions for Next Generation Molten Salt Reactors
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