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Advantages and disadvantages of using a focused ion beam to prepare TEM samples from irradiated U–10Mo monolithic nuclear fuel

Journal of nuclear materials, 2012-05, Vol.424 (1-3), p.38-42

2012

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Growth kinetics and microstructural evolution during hot isostatic pressing of U-10 wt.% Mo monolithic fuel plate in AA6061 cladding with Zr diffusion barrier

Journal of nuclear materials, 2014-04, Vol.447 (1-3), p.215-224

2014

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Microstructure of the irradiated U3Si2/Al silicide dispersion fuel

Journal of nuclear materials, 2011-12, Vol.419 (1-3), p.97-104

2011

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Are two heads better than one? Intellectual capital, learning and knowledge sharing in a dyadic interdisciplinary relationship

Journal of knowledge management, 2018-07, Vol.22 (6), p.1379-1407

2018

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Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7 wt%Mo dispersion fuels

Journal of nuclear materials, 2015-03, Vol.458 (C), p.115-121

2015

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Electron microscopy characterization of an as-fabricated research reactor fuel plate comprised of U–7Mo particles dispersed in an Al–2Si alloy matrix

Materials characterization, 2010-11, Vol.61 (11), p.1157-1166

2010

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Micro-tensile testing of the bond line in hot isostatic pressed aluminum

Journal of nuclear materials, 2022-04, Vol.561, p.153532, Article 153532

2022

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Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Journal of nuclear materials, 2017-08, Vol.492 (C), p.195-203

2017

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Impacts of annealing treatment on the microstructure of U-Mo monolithic fuel plates

Journal of nuclear materials, 2022-06, Vol.564, p.153687, Article 153687

2022

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Texture analyses and microstructural evolution in monolithic U-Mo nuclear fuel

Journal of nuclear materials, 2021-02, Vol.544, p.152677, Article 152677

2021

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Fabrication and characterization of dual phase magnesia–zirconia ceramics doped with plutonia

Journal of nuclear materials, 2006-06, Vol.352 (1-3), p.318-323

2006

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TEM characterization of irradiated U-7Mo/Mg dispersion fuel

Journal of nuclear materials, 2017-10, Vol.494 (C), p.380-397

2017

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Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils

Journal of nuclear materials, 2024-05, Vol.593 (15), p.155002, Article 155002

2024

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IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL

Nuclear Engineering and Technology, 2014, 46(2), , pp.169-182

2014

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Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils

Nuclear materials and energy, 2023-06, Vol.35, p.101436, Article 101436

2023

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Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier

Materials characterization, 2015-05, Vol.103 (C), p.50-57

2015

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Hysteresity effects in 3 mol% yttria-doped zirconia (t'-phase)

Journal of materials science, 1992-01, Vol.27 (15), p.4167-4174

1992

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Polycrystalline t'-ZrO2(Ln2O3) formed by displacive transformations

Journal of materials science, 1993-01, Vol.28 (16), p.4503-4509

1993

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Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Journal of nuclear materials, 2017-08, Vol.492 (C)

2017

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Fabrication of Monolithic RERTR Fuels by Hot Isostatic Pressing

Nuclear technology, 2010-11, Vol.172 (2), p.204-210, Article 204

2010

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Microstructural anomalies in hot-isostatic pressed U–10wt.% Mo fuel plates with Zr diffusion barrier

Materials characterization, 2015-05, Vol.103 (C), p.50-57

2015

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Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7wt%Mo dispersion fuels

Journal of nuclear materials, 2015-03, Vol.458 (C), p.115-121

2015

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Advantages and disadvantages of using a focused ion beam to prepare TEM samples from irradiated Ua10Mo monolithic nuclear fuel

Journal of nuclear materials, 2012-05 (1-3), p.38-42

2012

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Fabrication, Microstructural Characterization, and Mechanical Properties of Polycrystalline t'-Zirconia

Journal of the American Ceramic Society, 1990-12, Vol.73 (12), p.3650-3657

1990

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Low-Temperature Aging of t′-Zirconia: The Role of Microstructure on Phase Stability

Journal of the American Ceramic Society, 1991-08, Vol.74 (8), p.1811-1820

1991

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Advantages and disadvantages of using a focused ion beam to prepare TEM samples from irradiated U–10Mo monolithic nuclear fuel

Growth kinetics and microstructural evolution during hot isostatic pressing of U-10 wt.% Mo monolithic fuel plate in AA6061 cladding with Zr diffusion barrier

Microstructure of the irradiated U3Si2/Al silicide dispersion fuel

Are two heads better than one? Intellectual capital, learning and knowledge sharing in a dyadic interdisciplinary relationship

Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7 wt%Mo dispersion fuels

Electron microscopy characterization of an as-fabricated research reactor fuel plate comprised of U–7Mo particles dispersed in an Al–2Si alloy matrix

Micro-tensile testing of the bond line in hot isostatic pressed aluminum

Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Impacts of annealing treatment on the microstructure of U-Mo monolithic fuel plates

Texture analyses and microstructural evolution in monolithic U-Mo nuclear fuel

Fabrication and characterization of dual phase magnesia–zirconia ceramics doped with plutonia

TEM characterization of irradiated U-7Mo/Mg dispersion fuel

Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils

IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL

Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils

Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier

Hysteresity effects in 3 mol% yttria-doped zirconia (t'-phase)

Polycrystalline t'-ZrO2(Ln2O3) formed by displacive transformations

Irradiated microstructure of U-10Mo monolithic fuel plate at very high fission density

Fabrication of Monolithic RERTR Fuels by Hot Isostatic Pressing

Microstructural anomalies in hot-isostatic pressed U–10wt.% Mo fuel plates with Zr diffusion barrier

Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7wt%Mo dispersion fuels

Advantages and disadvantages of using a focused ion beam to prepare TEM samples from irradiated Ua10Mo monolithic nuclear fuel

Fabrication, Microstructural Characterization, and Mechanical Properties of Polycrystalline t'-Zirconia

Low-Temperature Aging of t′-Zirconia: The Role of Microstructure on Phase Stability

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