Casey McKinney
- Name
- Dr. Casey McKinney
- Institution
- Oak Ridge National Laboratory
- Position
- Postdoctoral Research Associate
- h-Index
- ORCID
- 0000-0003-3538-3614
- Expertise
- EBSD, EDS, Microscopy, Nuclear Materials
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"Characterization of solid fission products in 13.7% FIMA MOX fuel using electron microscopy techniques"
Riley Parrish, Karen Wright, Alexander Winston, Jason Harp, Casey McKinney, Assel Aitkaliyeva,
Journal of Nuclear Materials
Vol. 524
2019
67-79
Link
This work utilizes electron microscopy-based techniques to examine the radial behavior of solid fission products in plutonium (Pu) bearing mixed oxide (MOX) fuel irradiated to a burnup of 13.7% fissions per initial metal atom (FIMA). Metallic precipitates primarily consist of five fission products: ruthenium (Ru), rhodium (Rh), technetium (Tc), molybdenum (Mo), and palladium (Pd). The five metal precipitates (FMPs) examined in this work have low concentrations of Pd and Mo, with no major compositional differences along the fuel radius. A secondary Pd–Te metallic phase forms in cooler regions of the pellet, likely due to the diffusion of gaseous species away from the central void. X-ray chemical maps indicate that the Pd–Te phase can nucleate on the surface of FMPs before precipitating into separate particles. These particles were also found to alloy with iron (Fe) near the surface of the fuel pellet due to interdiffusion with the stainless-steel cladding. The insoluble perovskite oxide phase was found to form near the central void and at intermediate radial positions, but not at the fuel edge. These findings suggest that solid fission product phases form at varying counts and compositions along the fuel pellet radius, and thus should be considered when describing the thermal behavior of the fuel. |
| "Three-Dimensional Microstructural Characterization of the Peripheral Region in FBR MOX Fuel" Riley Parrish, Assel Aitkaliyeva, Casey McKinney, Materials in Nuclear Energy Systems (MiNES) October 6-10, (2019) Link |
NSUF Profile
This NSUF Profile is 70
NSUF Author
Authored an NSUF-supported publication
NSUF Presenter
Presented an NSUF-supported publication
Accomplished Submitter
Submitted 3+ RTE Proposals to NSUF
Top 5% Researcher
Top 5% of all RTE Proposals awarded
NSUF Collaborator
Collaborated on an RTE Proposal
Investigation of Fission Product Speciation in UN MiniFuel Particles - FY 2025 RTE 2nd Call, #25-5338
An Assessment of Radial Compositional Variations of the Grey Phase in FBR MOX Fuel Using EPMA - FY 2022 RTE 1st Call, #22-4388
Assessing the Radial Thermal Conductivity Change in FBR MOX Fuel - FY 2021 RTE 1st Call, #21-4304
Three-Dimensional Characterization of the Grey Phase in FBR MOX Fuel - FY 2019 RTE 3rd Call, #19-2861
3D Microstructure Reconstruction of the Peripheral Region of MOX FBR Fuel - FY 2019 RTE 1st Call, #19-1649
EPMA Characterization of Actinide Redistribution and Fission Product Composition in MOX Fuels - FY 2018 RTE 2nd Call, #18-1484
Advanced post-irradiation examination of accelerated burnup Cr-doped UO2 - FY 2025 CINR, #25-34159
Compositional and Defect Analysis of the FCCI in high burnup UO2 - FY 2023 RTE 1st Call, #23-4537
Investigation of fuel-cladding chemical interaction (FCCI) in irradiated U-Pu-Zr fuel - FY 2018 RTE 3rd Call, #18-1533