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Meeting MS&T25: Materials Science & Technology
Symposium Metallic Nuclear Fuel Design, Fabrication and Characterization
Presentation Title Exploring the Complex Interplay Between Phases, Porosity, and Thermal Properties in Metallic Fuels
Author(s) Assel Aitkaliyeva, Mitchell Mika, Allison Probert, Mary Sevart, Tiankai Yao, Ethan J Hisle, Tsvetoslav Pavlov, Cynthia Adkins, Karen Wright, Luca Capriotti
On-Site Speaker (Planned) Assel Aitkaliyeva
Abstract Scope Crystalline phase, porosity, and constituent redistribution impact the thermal behavior of irradiated U-Zr-based fuels, yet their individual effects remain poorly resolved. We conducted a detailed microstructural and thermal analysis of U-Zr-based fuels irradiated to various burnups and quantified phase composition, porosity, and local thermal conductivity as a function of radial position. Results reveal burnup-dependent changes in conductivity linked to phase transformations and porosity development. These findings provide new insights into thermal transport in irradiated metallic fuels that will inform the development of mechanistic property models critical for fuel performance simulation.

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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