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Highly thermally conductive and mechanically strong graphene fibers

Science (American Association for the Advancement of Science), 2015-09, Vol.349 (6252), p.1083-1087

2015

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Self-accelerated corrosion of nuclear waste forms at material interfaces

Nature materials, 2020-03, Vol.19 (3), p.310-316

2020

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Uncertainty quantification in multivariable regression for material property prediction with Bayesian neural networks

Scientific reports, 2024-05, Vol.14 (1), p.10543-10543, Article 10543

2024

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Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels

Scientific reports, 2023-06, Vol.13 (1), p.10616-10616, Article 10616

2023

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Long-term, sustainable solutions to radioactive waste management

Scientific reports, 2024-03, Vol.14 (1), p.5907-5907, Article 5907

2024

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An efficient instance segmentation approach for studying fission gas bubbles in irradiated metallic nuclear fuel

Scientific reports, 2023-12, Vol.13 (1), p.22275-22275, Article 22275

2023

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A fine pore-preserved deep neural network for porosity analytics of a high burnup U-10Zr metallic fuel

Scientific reports, 2023-12, Vol.13 (1), p.22274-22274, Article 22274

2023

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In-Plane Liftout and Push-to-Pull for In Situ Mechanical Testing of Irradiated Inconel X-750

Energies (Basel), 2024-09, Vol.17 (17), p.4199

2024

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Reply to: How much does corrosion of nuclear waste matrices matter

Nature materials, 2020-09, Vol.19 (9), p.962-963

2020

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The influence of lattice defects, recombination, and clustering on thermal transport in single crystal thorium dioxide

APL materials, 2020-11, Vol.8 (11), p.111103-111103-10

2020

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Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation

Energies (Basel), 2024-01, Vol.17 (1), p.197

2024

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Deciphering the degradation mechanism of the lead-free all inorganic perovskite Cs2SnI6

Npj Materials degradation, 2019-02, Vol.3 (1), Article 7

2019

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The advanced characterization, post-irradiation examination, and materials informatics for the development of ultra high-burnup annular U-10Zr metallic fuel

Frontiers in nuclear engineering, 2023-06, Vol.1

2023

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Corrosion interactions between stainless steel and lead vanado-iodoapatite nuclear waste form part I

Npj Materials degradation, 2020-05, Vol.4 (1), Article 13

2020

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A universal trend of structural, mechanical and electronic properties in transition metal (M=V, Nb, and Ta) borides: First-principle calculations

Computational materials science, 2012-12, Vol.65, p.302-308

2012

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Corrosion interactions between stainless steel and lead vanado-iodoapatite nuclear waste form part II

Npj Materials degradation, 2020-06, Vol.4 (1), Article 15

2020

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Metallization and softening of B6O at high pressure

Journal of alloys and compounds, 2014-07, Vol.600, p.71-77

2014

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Evolution of dislocation loops in irradiated α-Uranium: An atomistically-informed cluster dynamics investigation

Acta materialia, 2024-05, Vol.270, p.119728, Article 119728

2024

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Structural stability, phase transition, and mechanical and electronic properties of transition metal nitrides MN (M=Tc, Re, Os, and Ir): First-principles calculations

Computational materials science, 2012-04, Vol.56, p.116-121

2012

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First-principles study of structural stability, elastic and electronic properties of ternary rare earth-transition metal—Borides and carbides (RTxZ, R=Sc, Y, and La, T=Pt and Pd, Z=B and C, and x=2, 3, and 4)

Physica. B, Condensed matter, 2013-12, Vol.431, p.58-68

2013

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Transmission electron microscopy characterization of Fuel Cladding Chemical Interaction (FCCI) in ATR-irradiated HT9 clad U-10M (10M = 5Mo-4.3Ti-0.7Zr wt%) metallic fuel

Journal of nuclear materials, 2024-10, Vol.599, p.155209, Article 155209

2024

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Chemical durability and corrosion-induced microstructure evolution of compositionally complex titanate pyrochlore waste forms with uranium incorporation

Journal of the European Ceramic Society, 2024-02, Vol.44 (2), p.1102-1114

2024

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Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes

Journal of nuclear materials, 2023-12, Vol.586 (C), p.154675, Article 154675

2023

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Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction

Journal of nuclear materials, 2023-11, Vol.585 (C), p.154644, Article 154644

2023

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Chemical durability and corrosion-induced microstructure evolution of compositionally complex titanate pyrochlore waste forms with uranium incorporation

Journal of the European Ceramic Society, 2023-09, Vol.44 (2)

2023

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Highly thermally conductive and mechanically strong graphene fibers

Self-accelerated corrosion of nuclear waste forms at material interfaces

Uncertainty quantification in multivariable regression for material property prediction with Bayesian neural networks

Advanced characterization-informed machine learning framework and quantitative insight to irradiated annular U-10Zr metallic fuels

Long-term, sustainable solutions to radioactive waste management

An efficient instance segmentation approach for studying fission gas bubbles in irradiated metallic nuclear fuel

A fine pore-preserved deep neural network for porosity analytics of a high burnup U-10Zr metallic fuel

In-Plane Liftout and Push-to-Pull for In Situ Mechanical Testing of Irradiated Inconel X-750

Reply to: How much does corrosion of nuclear waste matrices matter

The influence of lattice defects, recombination, and clustering on thermal transport in single crystal thorium dioxide

Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation

Deciphering the degradation mechanism of the lead-free all inorganic perovskite Cs2SnI6

The advanced characterization, post-irradiation examination, and materials informatics for the development of ultra high-burnup annular U-10Zr metallic fuel

Corrosion interactions between stainless steel and lead vanado-iodoapatite nuclear waste form part I

A universal trend of structural, mechanical and electronic properties in transition metal (M=V, Nb, and Ta) borides: First-principle calculations

Corrosion interactions between stainless steel and lead vanado-iodoapatite nuclear waste form part II

Metallization and softening of B6O at high pressure

Evolution of dislocation loops in irradiated α-Uranium: An atomistically-informed cluster dynamics investigation

Structural stability, phase transition, and mechanical and electronic properties of transition metal nitrides MN (M=Tc, Re, Os, and Ir): First-principles calculations

First-principles study of structural stability, elastic and electronic properties of ternary rare earth-transition metal—Borides and carbides (RTxZ, R=Sc, Y, and La, T=Pt and Pd, Z=B and C, and x=2, 3, and 4)

Transmission electron microscopy characterization of Fuel Cladding Chemical Interaction (FCCI) in ATR-irradiated HT9 clad U-10M (10M = 5Mo-4.3Ti-0.7Zr wt%) metallic fuel

Chemical durability and corrosion-induced microstructure evolution of compositionally complex titanate pyrochlore waste forms with uranium incorporation

Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes

Characterization of micro-burnup treat irradiated U-22.5 at.% Zr and U-52.8 at.% Zr foils by transmission electron microscopy and X-ray diffraction

Chemical durability and corrosion-induced microstructure evolution of compositionally complex titanate pyrochlore waste forms with uranium incorporation

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