Three-dimensional microstructural characterization of FBR MOX fuel and the contribution of microstructural features to the thermal conductivity of the fuel

Casey McKinney, Floyd Hilty, Daniel Murray, Narayan Poudel, Fabiola Cappia, Tsvetoslav Pavlov, Assel Aitkaliyeva

Research output: Contribution to journalArticlepeer-review

4 Scopus citations

Abstract

Combination of microstructural characterization, property measurements, and phase field modeling is used to investigate fast breeder reactor (FBR) mixed oxide (MOX) fuel irradiated to burnup of 13.7% fissions per initial metal atom (FIMA). The fuel was characterized at different radial locations, which revealed that grey phase can be present in the central region if it nucleates on five metal precipitates (FMPs). In addition, in the mid-radial region FMPs do not diffuse out of the region once formed and the size of Pd–Te precipitates is dictated by the porosity present in the region. Thermal conductivity measurements (TCM) were conducted as a function of radial location and the microstructure of the fuel was correlated with the observed trend. Reconstructions of the 3D solid and gaseous fission product structures in different regions of the fuel were used to simulate the effective thermal conductivity (ETC) of the respective regions and determine which microstructural feature has the strongest impact on thermal conductivity. Based on conducted assessment, FMPs and Pd-Te precipitates improve local conductivity of central and mid-radial regions even in the presence of grey phase, but defects are primary contributor to the degradation of thermal conductivity on the periphery of the fuel.

Original languageEnglish
Article number154073
JournalJournal of Nuclear Materials
Volume572
DOIs
StatePublished - Dec 15 2022
Externally publishedYes

Funding

This work was supported by the U.S. Department of Energy , Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07-051D14517 as part of a Nuclear Science User Facilities experiment.

FundersFunder number
U.S. Department of EnergyDE-AC07-051D14517
Office of Nuclear Energy

    Keywords

    • 3D microstructure
    • Defects
    • Fission products
    • MOX fuel
    • Thermal conductivity

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