About this Abstract |
Meeting |
2025 TMS Annual Meeting & Exhibition
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Symposium
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Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
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Presentation Title |
Investigation of Fuel Cladding Chemical Interactions with UO2 and Doped UO2 Using Diffusion Couples |
Author(s) |
Rebecca Manns, Josephine Libero-Cruzado, Daniel Koury |
On-Site Speaker (Planned) |
Rebecca Manns |
Abstract Scope |
As part of a study looking at fuel cladding chemical interactions (FCCIs), uranium oxide (UO2) and doped uranium oxide pellets were placed into diffusion couples alongside cladding materials of interest such as Zircaloy and stainless steels. The diffusion couples were sealed in quartz tubing under vacuum, annealed at various temperatures, quenched, and then cut into cross sections. Cross sections were prepared using standard metallographic practices and were analyzed using a scanning electron microscope (SEM) equipped with energy dispersive x-ray spectroscopy (EDS). SEM and EDS were used to examine the concentration profiles of the diffusion zones, the resulting phases, and the general diffusion behavior of the systems. The integrated diffusion coefficients, interdiffusion coefficients, and activation energies were calculated. The results of this study provide critical information about the fuel cladding chemical interactions and offer a comparison between UO2, a well-established fuel, and doped UO2, a candidate fuel. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Characterization, Other |