Master (Spark Plasma) Sintering Curve of UO2 and UO2-10 Vol. % Mo Fuel Material

Abstract UO2-molybdenum (Mo) composites are being considered for accident tolerant fuel (ATF) applications in commercial nuclear reactors. In this study, UO2-10 vol. % Mo was fabricated using spark plasma sintering (SPS), where the particle size of Mo was varied between 30 nm, 60 nm, 100 nm, and 150 μm, to study its effect on the densification of the UO2-10 vol. % Mo composite. A decrease in Mo particle size was identified to cause a shift in densification peaks in UO2-Mo toward higher temperature, due to the Mo particles coating the bigger UO2 particles. The in situ ram displacement data was used to construct a master sintering curve (MSC), which was validated using additional SPS trials. The accuracy of the MSC was measured by the standard deviation between prediction and experimentally observed data, which varied from 0.7% to 4.8%.

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Publication Details

Journal
Journal of Nuclear Engineering and Radiation Science
Published
2025-04-09
DOI
https://doi.org/10.1115/1.4068390
Primary Topic
Nuclear Materials and Properties
Type
article
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article

Master (Spark Plasma) Sintering Curve of UO2 and UO2-10 Vol. % Mo Fuel Material

Charles Liu, Anil Prasad, Lukas Bichler, Jerzy A. Szpunar et al.
Journal of Nuclear Engineering and Radiation Science
Nuclear Materials and Properties
article

Master (Spark Plasma) Sintering Curve of UO2 and UO2-10 Vol. % Mo Fuel Material

Charles Liu, Anil Prasad, Lukas Bichler, Jerzy A. Szpunar, Murali Krishna Tummalapalli, Linu Malakkal
article en

Abstract

Abstract UO2-molybdenum (Mo) composites are being considered for accident tolerant fuel (ATF) applications in commercial nuclear reactors. In this study, UO2-10 vol. % Mo was fabricated using spark plasma sintering (SPS), where the particle size of Mo was varied between 30 nm, 60 nm, 100 nm, and 150 μm, to study its effect on the densification of the UO2-10 vol. % Mo composite. A decrease in Mo particle size was identified to cause a shift in densification peaks in UO2-Mo toward higher temperature, due to the Mo particles coating the bigger UO2 particles. The in situ ram displacement data was used to construct a master sintering curve (MSC), which was validated using additional SPS trials. The accuracy of the MSC was measured by the standard deviation between prediction and experimentally observed data, which varied from 0.7% to 4.8%.

Journal of Nuclear Engineering and Radiation ScienceVol. 11(3)
University of British Columbia (CA), Idaho National Laboratory (US), University of Saskatchewan (CA), Canadian Nuclear Laboratories (CA), University of British Columbia, Okanagan Campus (CA), Canadian Nuclear Laboratories (CA), Okanagan University College (CA)
Openalex Percentile: Top 95%
Nuclear Materials and Properties
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