Publications

(2022). High-temperature Compressive Creep Tests of U3Si2 with Spark Plasma Sintering: Experiments and Finite Element Modeling. Journal of Nuclear Materials.

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(2021). Characterizing Topics in Social Media Using Dynamics of Conversation. Entropy.

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(2021). Micro-cantilever beam experiments and modeling in porous polycrystalline UO2. Journal of Nuclear Materials.

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(2021). Aluminum-doped U3Si2 composite fuels with enhanced oxidation resistance. Journal of Alloys and Compounds.

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(2021). Elevated Temperature Nanoindentation Creep Study of Plastically Deformed and Spark Plasma Sintered UO2. Journal of Nuclear Materials.

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(2021). Machine learning-enabled prediction of chemical durability of A2B2O7 pyrochlore and fluorite. Journal of Nuclear Materials.

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(2021). Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering. Journal of Nuclear Materials.

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(2021). Dense nanocrystalline UO2+x fuel pellets synthesized by high pressure spark plasma sintering. Journal of Nuclear Materials.

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(2021). Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance. Journal of Nuclear Materials.

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(2021). A systematic study of lanthanide titanates (A2Ti2O7) chemical durability: corrosion mechanisms and control parameters. Corrosion Science.

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(2021). 3Y-TZP Toughened and Oxidation-resistant U3Si2 Composites for Accident Tolerant Fuels. Journal of Nuclear Materials.

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(2020). U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels. Journal of Nuclear Materials.

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(2020). Development of a grain growth model for U3Si2 using experimental data, phase field simulation and molecular dynamics. Journal of Nuclear Materials.

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(2020). Cr-doped U3Si2 composite fuels under steam corrosion. Corrosion Science.

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(2020). UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance. Ceramics International.

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(2020). Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering. Journal of Alloys and Compounds.

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(2020). Spark plasma sintering (SPS) densified U3Si2 pellets: Microstructure control and enhanced mechanical and oxidation properties. Journal of Alloys and Compounds.

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(2019). Nano-and micro-indentation testing of sintered UO2 fuel pellets. Journal of Nuclear Materials.

Project

(2019). In situ Investigation of Water Interaction with Lead-Free All Inorganic Perovskite (Cs2SnIxCl6-x). The Journal of Physical Chemistry C.

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(2019). Deciphering the degradation mechanism of the lead-free all inorganic perovskite Cs2SnI6. npj Materials Degradation.

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(2018). Thermally-conductive and mechanically-robust graphene nanoplatelet reinforced UO2 composite nuclear fuels. Scientific reports.

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(2018). Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature. Journal of Nuclear Materials.

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(2018). In-situ TEM study of the ion irradiation behavior of U3Si2 and U3Si5. Journal of Nuclear Materials.

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(2018). Consolidation of commercial-size UO2 fuel pellets using spark plasma sintering and microstructure/microchemical analysis. MRS Communications.

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(2017). Radiation-induced grain subdivision of U3Si2 irradiated by 300 keV Xe+ at LWR temperature. Transactions of the American Nuclear Society.

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(2016). Effects of microstructural constraints on the transport of fission products in uranium dioxide at low burnups. Journal of Nuclear Materials.

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