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Meeting MS&T25: Materials Science & Technology
Symposium Ceramic Materials for Nuclear Energy System
Presentation Title In Situ High-Temperature Behavior of Uranium Borides
Author(s) Riley Moeykens, Axel Tran, Anthony Albert Harrup, Mehmet Topsakal, Bruce Ravel, Ericmoore E. Jossou
On-Site Speaker (Planned) Ericmoore E. Jossou
Abstract Scope In recent years, uranium borides have emerged as promising candidate fuel forms due to their high thermal conductivity, high melting points, high uranium density, and potential dual functionality as both fuel and burnable absorbers. This work investigates the synthesis, structural behavior, and oxidation resistance of uranium borides and chromium-alloyed uranium borides. The temperature-dependent structural evolution of these materials was characterized using in situ synchrotron X-ray powder diffraction and X-ray absorption fine structure spectroscopy. This talk outlines the methods and challenges associated with synthesizing uranium borides and chromium-alloyed uranium borides, and evaluates their thermophysical properties and oxidation behavior, providing insights into their potential as advanced nuclear fuel forms.

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

Analysis of Crucible-Scale Corrosion Testing of Monofrax® K-3 Refractory in Contact with Glass Melts
Chemical Durability of Cermet Waste Forms for Advanced Reactor Wastes
Cluster Dynamics Modeling of Extended Defect Evolution with Loop Unfaulting in Proton-Irradiated Single Crystal ThO2
Dechlorination and Immobilization of Electrorefiner Salt Waste in Phosphate Glass Matrices
In Situ High-Temperature Behavior of Uranium Borides
Point Defect Energetics in AlGaN Alloys by Machine Learning Force Field
Stabilization of Research Reactor Spent Nuclear Fuel to Ceramic Form for Potential Disposal in a Deep Geological Repository
Swift Heavy Ions to Study Amorphization Behavior of Compositionally Complex Oxides
Synthesis and Characterization of Rhenium Chalcogenides for Nuclear Waste Management
The Role of Microstructures in Hydrogen Retention in Zirconium Hydride Moderator

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