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Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe

Journal of nuclear materials, 2015-09, Vol.464 (C), p.236-244

2015

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Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel

Nuclear materials and energy, 2023-09, Vol.36, p.101469, Article 101469

2023

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Aluminum cladding oxide growth prediction for high flux research reactors

Journal of nuclear materials, 2020-02, Vol.529 (C), p.151926, Article 151926

2020

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Cross section TEM characterization of high-energy-Xe-irradiated U-Mo

Journal of nuclear materials, 2017-05, Vol.488 (C), p.134-142

2017

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Microstructure of as atomized and annealed U-Mo7 particles: A SEM/EBSD study of grain growth

Journal of nuclear materials, 2017-11, Vol.495 (C), p.249-266

2017

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Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation

Journal of nuclear materials, 2021-02, Vol.544 (C), p.152684, Article 152684

2021

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Migration of minor actinides and lanthanides in fast reactor metallic fuel

Journal of nuclear materials, 2009-07, Vol.392 (2), p.164-170

2009

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Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation

Journal of nuclear materials, 2020-02, Vol.529 (C), p.151945, Article 151945

2020

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High-energy synchrotron study of in-pile-irradiated U–Mo fuels

Scripta materialia, 2016-03, Vol.114, p.146-150

2016

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U–Mo alloy fuel for TRU-burning advanced fast reactors

Journal of nuclear materials, 2013-10, Vol.441 (1-3), p.520-524

2013

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Lanthanides migration and immobilization in U–Zr nuclear fuels

Journal of nuclear materials, 2012-06, Vol.425 (1-3), p.188-192

2012

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Thermal creep modeling of HT9 steel for fast reactor applications

Journal of nuclear materials, 2011-02, Vol.409 (3), p.207-213

2011

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Lanthanides migration in U–Zr based nuclear fuels

Journal of nuclear materials, 2010-12, Vol.407 (3), p.228-231

2010

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Modeling of constituent redistribution in U–Pu–Zr metallic fuel

Journal of nuclear materials, 2006-12, Vol.359 (1), p.17-28

2006

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Derivation of kinetic coefficients by atomistic methods for studying defect behavior in Mo

Journal of nuclear materials, 2012-06, Vol.425 (1-3), p.41-47

2012

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Atomistic modeling of the interaction of cladding elements (Fe, Ni, Cr) with U–Zr fuel

Journal of nuclear materials, 2011-07, Vol.414 (2), p.101-108

2011

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Atomistic modeling and simulation of the role of Be and Bi in Al diffusion in U–Mo fuel

Journal of nuclear materials, 2011-07, Vol.414 (2), p.179-185

2011

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Surface properties, thermal expansion, and segregation in the U–Zr solid solution

Computational materials science, 2010-12, Vol.50 (2), p.447-453

2010

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Fission gas transport and its interactions with irradiation-induced defects in lanthanum doped ceria

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2012-02, Vol.272, p.239-243

2012

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The effects of xenon implantation in ceria with and without lanthanum

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2012-02, Vol.272, p.236-238

2012

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On the use of Fresnel boundary and interface conditions in radiative-transfer calculations for multilayered media

Journal of quantitative spectroscopy & radiative transfer, 2008-03, Vol.109 (5), p.752-769

2008

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Radiative transfer in a multi-layer medium subject to Fresnel boundary and interface conditions and uniform illumination by obliquely incident parallel rays

Journal of quantitative spectroscopy & radiative transfer, 2008-08, Vol.109 (12), p.2151-2170

2008

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Modeling and analysis of mixed-material surface evolution and sputtering

Journal of nuclear materials, 2005-03, Vol.337-339, p.1048-1052

2005

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Analysis of constituent redistribution in U-Pu-Zr metallic fuel

Journal of nuclear materials, 2006-01, Vol.359 (1 ; 2006)

2006

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Near-surface compositional modifications of ternary alloys during sputtering at elevated temperatures

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 1989-05, Vol.42 (1), p.49-60

1989

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Irradiation behavior study of U–Mo/Al dispersion fuel with high energy Xe

Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel

Aluminum cladding oxide growth prediction for high flux research reactors

Cross section TEM characterization of high-energy-Xe-irradiated U-Mo

Microstructure of as atomized and annealed U-Mo7 particles: A SEM/EBSD study of grain growth

Temperature Effects on Interdiffusion of Al and U-Mo under Irradiation

Migration of minor actinides and lanthanides in fast reactor metallic fuel

Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation

High-energy synchrotron study of in-pile-irradiated U–Mo fuels

U–Mo alloy fuel for TRU-burning advanced fast reactors

Lanthanides migration and immobilization in U–Zr nuclear fuels

Thermal creep modeling of HT9 steel for fast reactor applications

Lanthanides migration in U–Zr based nuclear fuels

Modeling of constituent redistribution in U–Pu–Zr metallic fuel

Derivation of kinetic coefficients by atomistic methods for studying defect behavior in Mo

Atomistic modeling of the interaction of cladding elements (Fe, Ni, Cr) with U–Zr fuel

Atomistic modeling and simulation of the role of Be and Bi in Al diffusion in U–Mo fuel

Surface properties, thermal expansion, and segregation in the U–Zr solid solution

Fission gas transport and its interactions with irradiation-induced defects in lanthanum doped ceria

The effects of xenon implantation in ceria with and without lanthanum

On the use of Fresnel boundary and interface conditions in radiative-transfer calculations for multilayered media

Radiative transfer in a multi-layer medium subject to Fresnel boundary and interface conditions and uniform illumination by obliquely incident parallel rays

Modeling and analysis of mixed-material surface evolution and sputtering

Analysis of constituent redistribution in U-Pu-Zr metallic fuel

Near-surface compositional modifications of ternary alloys during sputtering at elevated temperatures

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