"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. |
"Chemical and microstructural analysis of irradiated mixed oxide fuels" Assel Aitkaliyeva, Riley Parrish, Jason Harp, The Minerals, Metals and Materials Society (TMS) Annual Meeting & Exhibition March 11-15, (2018) | |
"Microstructural analysis of irradiated mixed oxide fuels" Riley Parrish, Assel Aitkaliyeva, Jason Harp, NuMat 2018 October 14-18, (2018) | |
"TEM Analysis of Irradiated Mixed-oxide Fuel" Assel Aitkaliyeva, Riley Parrish, Jason Harp, American Nuclear Society Student Conference 2018 April 5-7, (2018) | |
"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 |
U.S. DOE Nuclear Science User Facilities Awards 30 Rapid Turnaround Experiment Research Proposals - Awards total nearly $1.2 million The U.S. Department of Energy (DOE) Nuclear Science User Facilities (NSUF) has selected 30 new Rapid Turnaround Experiment (RTE) projects, totaling up to approximately $1.2 million. These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Wednesday, April 26, 2017 - Calls and Awards |
U.S. DOE Nuclear Science User Facilities Awards 35 Rapid Turnaround Experiment Research Proposals - Awards total approximately $1.3 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Wednesday, September 20, 2017 - Calls and Awards |
DOE Awards 33 Rapid Turnaround Experiment Research Proposals - Projects total approximately $1.5 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Monday, May 14, 2018 - Calls and Awards |
DOE Awards 33 Rapid Turnaround Experiment Research Proposals - Projects total approximately $1.2 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Monday, June 18, 2018 - Calls and Awards |
DOE awards 39 RTE Projects - Projects total approximately $1.3 million Thursday, February 1, 2018 - Calls and Awards |
Microstructural characterization of ~7% burn-up MOX fuel - FY 2018 RTE 1st Call, #1179
Microstructural characterization of 13% burn-up MOX fuel - FY 2017 RTE 3rd Call, #1042
Microstructural characterization of 21% burn-up MOX fuel - FY 2017 RTE 3rd Call, #1043
Microstructural characterization of 23% burn-up MOX fuel - FY 2017 RTE 1st Call, #812
Microstructural characterization of 3% burn-up MOX fuel - FY 2017 RTE 2nd Call, #909
TEM analysis of Irradiated MOX fuel - FY 2018 RTE 2nd Call, #1370
TEM Characterization of High Burnup MOX Fuel - FY 2018 RTE 3rd Call, #1556
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
Privacy and Accessibility · Vulnerability Disclosure Program