Search Results - "Smith, Charlyne"
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1
Microstructural dependence on fuel matrix composition in irradiated U-Mo dispersion fuels
Published in Journal of nuclear materials (01-07-2021)“…Microstructural characterization of U-Mo dispersion fuel plates irradiated in the RERTR-7 experiment in the Advanced Test Reactor was performed to study the…”
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2
High burnup structure formation in U-Mo fuels
Published in Journal of nuclear materials (01-05-2022)“…This study used electron microscopy techniques and phase field modeling to investigate the mechanisms responsible for developing the high burnup structure in…”
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3
Microstructural response of the fuel phase in U-7Mo dispersion fuel irradiated at different powers
Published in Journal of nuclear materials (15-12-2020)“…Irradiation conditions such as fission power, fission rates, and temperature are important parameters for nuclear fuels because they influence the…”
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4
New approach for measuring interconnectivity of fission gas pores in nuclear fuels from 2D micrographs
Published in Journal of materials science (2021)“…In this work, we developed a simple and easily reproducible method to measure the interconnectivity of fission gas pore phases in irradiated nuclear fuels. The…”
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5
Comparison of manual and automated image analysis techniques for characterization of fission gas pores in irradiated U-Mo fuels
Published in Micron (Oxford, England : 1993) (01-04-2019)“…•Image analysis of pore size distribution was conducted for irradiated U-Mo fuels.•Automated image analysis techniques were evaluated against ASTME562 standard…”
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6
Early self-organization of fission gas bubble superlattice formation in neutron-irradiated monolithic U-10Mo fuels
Published in Journal of nuclear materials (01-05-2023)“…Self-organization of defect superlattices in far-from-equilibrium systems presents a promising way to mitigate swelling concerns in nuclear materials. The gas…”
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7
Irradiation behavior of ground and atomized U-7Mo dispersion fuels irradiated to low burnup
Published in Nuclear engineering and design (15-04-2024)“…•Mg replacement for Al-Si matrices effectively restrains FMI layer formation.•Differences in FGP morpohology between ground and atomized fuels may result from…”
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8
A practical guide to characterizing irradiated nuclear fuels using FIB tomography
Published in Micron (Oxford, England : 1993) (01-07-2022)“…Focused ion beam (FIB) tomography with combined electron backscatter diffraction (EBSD) and energy dispersive x-ray spectroscopy (EDS) is a technique capable…”
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9
A critical review of the microstructure of U–Mo fuels
Published in Journal of nuclear materials (01-11-2020)“…The microstructure of fuels evolves with irradiation and extensive microstructural characterization has been performed both on as-fabricated and irradiated…”
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10
A practical guide to characterizing irradiated nuclear fuels using FIB tomography
Published in Micron (Oxford, England : 1993) (25-04-2022)“…We report focused ion beam (FIB) tomography with combined electron backscatter diffraction (EBSD) and energy dispersive x-ray spectroscopy (EDS) is a technique…”
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Journal Article -
11
Possible impacts of Mo chemical banding and second phase impurities on the irradiation behavior of monolithic U-10Mo fuels
Published in Journal of nuclear materials (01-04-2023)“…This study investigated the microstructural behavior of both full-size and mini-size monolithic U-10Mo fuel plates irradiated to high burnup with a focus on…”
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Journal Article -
12
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup
Published in Journal of nuclear materials (01-03-2023)“…This study investigated possible failure mode sequences in U-10Mo monolithic fuel irradiated to very-high-burnup. The U-Mo fuel plate used in this study was…”
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13
The role of UC inclusions in the development of fission gas bubble superlattice neutron-irradiated monolithic U-10Mo fuels
Published in Journal of nuclear materials (01-08-2023)“…Uranium Carbide (UC) inclusions are the most prevalent impurities in Uranium-Molybdenum (U-Mo) fuel and are considered undesirable because they could…”
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14
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup
Published in Journal of nuclear materials (15-12-2022)“…Here, this study investigated possible failure mode sequences in U-10Mo monolithic fuel irradiated to very-high-burnup. The U-Mo fuel plate used in this study…”
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Journal Article -
15
Evidence of Xe-incorporation in the bubble superlattice in irradiated U-Mo fuel
Published in Journal of nuclear materials (15-12-2023)“…For years, researchers have reported competing ideas on the formation of fission gas bubble superlattices in metallic fuels, which was postulated to be…”
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Journal Article -
16
Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel
Published in Journal of nuclear materials (19-10-2023)“…Here, advanced microstructural characterization techniques, such as scanning electron microscopy (SEM) and scanning transmission electron microscopy - energy…”
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17
Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel
Published in Journal of nuclear materials (01-01-2024)Get full text
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18
Microstructural Characterization of Irradiated U-Mo Fuels
Published 01-01-2021“…Low enriched uranium-molybdenum (U-Mo) fuel is being investigated to replace highly enriched uranium fuels in high-performance research and test reactors. The…”
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Dissertation -
19
Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils
Published in Nuclear materials and energy (01-06-2023)“…•Heat treatment influence on the microstructure of irradiated U-Mo fuel specimens was investigated.•Irradiation induced grain refining is influenced by the…”
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Journal Article