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Meeting MS&T25: Materials Science & Technology
Symposium Metallic Nuclear Fuel Design, Fabrication and Characterization
Presentation Title Three-Dimensional Microstructural Evolution of Irradiated U-10Zr Nuclear Fuel Revealed by Synchrotron X-ray Micro-CT
Author(s) Anthony Albert Harrup Gutiérrez, Riley Moeykens, Jana Cu Howard, Michael Drakopoulos, Tiankai Yao, Ericmoore Jossou
On-Site Speaker (Planned) Anthony Albert Harrup Gutiérrez
Abstract Scope Uranium-Zirconium (U-10Zr) is the leading candidate fuel for Sodium Fast Reactors due to its high thermal conductivity and high fuel burnup potential. Understanding its microstructural evolution under irradiation is essential for evaluating in-reactor performance and safety. In this work, we utilize high-resolution synchrotron X-ray micro-computed tomography (micro-CT) to investigate the three-dimensional evolution of porosity and microstructural changes in irradiated U-10Zr fuel. This non-destructive technique (micro-CT) reveals features such as pore growth, phase redistribution, and Fuel-Cladding Chemical Interaction. Quantitative analysis of these features provides insights into the mechanisms driving fuel degradation under reactor-relevant conditions. Finally, by coupling the 3D microstructure with thermal conductivity simulation, we assess the impact of evolving microstructure on heat transport in the fuel. These findings enhance our understanding of fuel performance during reactor operation and aid in the design of next generation of metallic fuels with improved operational efficiency.

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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