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Meeting MS&T25: Materials Science & Technology
Symposium Metallic Nuclear Fuel Design, Fabrication and Characterization
Presentation Title High Temperature Structures, Oxidation, and Thermodynamics of Uranium Fuels
Author(s) Xiaofeng Guo, Emma Kindall, Natalie Yaw, Sam Karcher, Malin C. Wilkins, John S. McCloy, Adrien J. Terricabras, Scarlett Widgeon Paisner, Arjen van Veelen, Hongwu Xu, Joshua T. White
On-Site Speaker (Planned) Xiaofeng Guo
Abstract Scope New uranium fuels (including UC and UN) share several key characteristics with the industry standard uranium oxide. A fundamental understanding of the material chemistry and thermodynamic properties of uranium carbides and uranium nitrides is critical for predicting their behavior under reactor, off-normal, or storage conditions. In this work, we investigated (1) the thermal oxidation pathways of UC and UN by thermogravimetric analysis (TGA), and in situ X-ray diffraction (XRD) and ex situ X-ray absorption fine structure, (2) the high temperature structures and the thermal expansion coefficients (CTE) of UC and UN under oxidizing conditions, (3) the uncommon uranium carbide phases for their high temperature structures and CTE by in situ neutron diffraction, and (4) the potential U(CxO1-x)2 phase formation and equilibrium, with some thoughts about thermodynamic completeness of U-C-O system.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Advanced Characterization of Pu Oxidation with S/TEM
Characterization of High Uranium Density Compositionally Complex Refractory Alloys
Exploring the Complex Interplay Between Phases, Porosity, and Thermal Properties in Metallic Fuels
High Temperature Structures, Oxidation, and Thermodynamics of Uranium Fuels
Impact of Dislocation Loops on the Thermal Transport in Nuclear Fuels: A First-Principles Atomistic Approach
Metal Fuel Performance in Sodium Fast Reactors: Post-Irradiation Examination and Innovative Experiments
Mitigating FCCI in Metallic Fuels: Evaluating Cladding Liners Using Multiscale Modeling
Multi-scale modeling of wastage layer formation in metallic fuel cladding
Multiscale fuel performance modeling of U-Mo fuel for research reactors
Nitinol as Surrogate for Laser Additive Manufacturing of Uranium-10 Zirconium Metallic Nuclear Fuel
Perspectives on Accelerated Fuel Irradiation Testing in Uranium-Zirconium Alloys
Refractory Systems in Uranium-Containing Alloys for High Temperature Metallic Fuel
Thermal transport of uranium nitride (UN) after irradiation
Three-Dimensional Microstructural Evolution of Irradiated U-10Zr Nuclear Fuel Revealed by Synchrotron X-ray Micro-CT
Understanding grain refinement and gas bubble evolution in U-10Mo fuel using phase-field modeling
Volume fraction of porosity and distinct phases in irradiated FAST U-Zr fuel using manual point counting and automatic image analysis

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