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Phase stability of an HT-9 duct irradiated in FFTF

Journal of nuclear materials, 2012-11, Vol.430 (1-3), p.194-204

2012

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Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure

Journal of nuclear materials, 2000, Vol.276 (1), p.123-142

2000

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Interdiffusion and reaction between uranium and iron

Journal of nuclear materials, 2012-05, Vol.424 (1-3), p.82-88

2012

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Emulation of reactor irradiation damage using ion beams

Scripta materialia, 2014-10, Vol.88 (C), p.33-36

2014

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Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443 °C

Journal of nuclear materials, 2009-09, Vol.393 (2), p.235-241

2009

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Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF

Journal of nuclear materials, 2011-07, Vol.414 (2), p.237-242

2011

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Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions

Journal of nuclear materials, 2014-10, Vol.453 (1-3), p.176-181

2014

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The effect of oversized solute additions on the microstructure of 316SS irradiated with 5 MeV Ni ++ ions or 3.2 MeV protons

Journal of nuclear materials, 2004-02, Vol.325 (2), p.94-106

2004

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Effects of Cr and Ni on interdiffusion and reaction between U and Fe–Cr–Ni alloys

Journal of nuclear materials, 2014-08, Vol.451 (1-3), p.372-378

2014

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The influence of oversized solute additions on radiation-induced changes and post-irradiation intergranular stress corrosion cracking behavior in high-purity 316 stainless steels

Journal of nuclear materials, 2003-09, Vol.321 (2), p.192-209

2003

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Proton irradiation damage of an annealed Alloy 718 beam window

Journal of nuclear materials, 2015-04, Vol.459 (C), p.103-113

2015

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Cross-sectional TEM and X-ray examination of radiation-induced stress relaxation of peened stainless steel surfaces

Journal of nuclear materials, 2005-02, Vol.336 (2), p.314-322

2005

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The influence of explosive-driven shock prestraining at 35 GPa and of high deformation on the structure/property behavior of 316 L austenitic stainless steel

Metallurgical and materials transactions. A, Physical metallurgy and materials science, 2005-07, Vol.36 (7), p.1825-1831

2005

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Diffusional Interaction Between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C)

Metallurgical and materials transactions. A, Physical metallurgy and materials science, 2015-01, Vol.46 (1), p.72-82

2015

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Correlation of radiation-induced changes in mechanical properties and microstructural development of Alloy 718 irradiated with mixed spectra of high-energy protons and spallation neutrons

Journal of nuclear materials, 2001-07, Vol.296 (1), p.145-154

2001

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Microstructural origins of radiation-induced changes in mechanical properties of 316 L and 304 L austenitic stainless steels irradiated with mixed spectra of high-energy protons and spallation neutrons

Journal of nuclear materials, 2001-07, Vol.296 (1), p.112-118

2001

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The effect of grain boundary character distribution on the high temperature deformation behavior of Ni–16Cr–9Fe alloys

Acta materialia, 2003-08, Vol.51 (13), p.3831-3848

2003

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Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates

Journal of nuclear materials, 2015-12, Vol.467 (Part 2), p.692-702

2015

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Proton irradiation emulation of PWR neutron damage microstructures in solution annealed 304 and cold-worked 316 stainless steels

Journal of nuclear materials, 2003-11, Vol.323 (1), p.18-28

2003

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Orientation dependence of shock-induced twinning and substructures in a copper bicrystal

Acta materialia, 2010, Vol.58 (2), p.549-559

2010

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Microstructural evolution in modified 9Cr–1Mo ferritic/martensitic steel irradiated with mixed high-energy proton and neutron spectra at low temperatures

Journal of nuclear materials, 2002-12, Vol.307, p.266-271

2002

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Compositional and temperature dependence of void swelling in model Fe–Cr base alloys irradiated in the EBR-II fast reactor

Journal of nuclear materials, 2000-12, Vol.283-287, p.164-168

2000

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Microstructural evolution of Alloy 718 at high helium and hydrogen generation rates during irradiation with 600–800 MeV protons

Journal of nuclear materials, 2000-12, Vol.283-287, p.324-328

2000

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Diffusional Interaction between U-10 wt.% Zr and Fe at 903K, 923K and 953K (630°C, 650°C, and 680°C)

Metallurgical and materials transactions. A, Physical metallurgy and materials science, 2014-04, Vol.46 (1)

2014

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Characterization of U-Pu-Zr and U-Pu-Mo Fuel Alloys in Transmission Electron Microscope

Microscopy and microanalysis, 2013-08, Vol.19 (S2), p.1740-1741

2013

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Phase stability of an HT-9 duct irradiated in FFTF

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure

Interdiffusion and reaction between uranium and iron

Emulation of reactor irradiation damage using ion beams

Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443 °C

Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF

Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions

The effect of oversized solute additions on the microstructure of 316SS irradiated with 5 MeV Ni ++ ions or 3.2 MeV protons

Effects of Cr and Ni on interdiffusion and reaction between U and Fe–Cr–Ni alloys

The influence of oversized solute additions on radiation-induced changes and post-irradiation intergranular stress corrosion cracking behavior in high-purity 316 stainless steels

Proton irradiation damage of an annealed Alloy 718 beam window

Cross-sectional TEM and X-ray examination of radiation-induced stress relaxation of peened stainless steel surfaces

The influence of explosive-driven shock prestraining at 35 GPa and of high deformation on the structure/property behavior of 316 L austenitic stainless steel

Diffusional Interaction Between U-10 wt pct Zr and Fe at 903 K, 923 K, and 953 K (630 °C, 650 °C, and 680 °C)

Correlation of radiation-induced changes in mechanical properties and microstructural development of Alloy 718 irradiated with mixed spectra of high-energy protons and spallation neutrons

Microstructural origins of radiation-induced changes in mechanical properties of 316 L and 304 L austenitic stainless steels irradiated with mixed spectra of high-energy protons and spallation neutrons

The effect of grain boundary character distribution on the high temperature deformation behavior of Ni–16Cr–9Fe alloys

Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates

Proton irradiation emulation of PWR neutron damage microstructures in solution annealed 304 and cold-worked 316 stainless steels

Orientation dependence of shock-induced twinning and substructures in a copper bicrystal

Microstructural evolution in modified 9Cr–1Mo ferritic/martensitic steel irradiated with mixed high-energy proton and neutron spectra at low temperatures

Compositional and temperature dependence of void swelling in model Fe–Cr base alloys irradiated in the EBR-II fast reactor

Microstructural evolution of Alloy 718 at high helium and hydrogen generation rates during irradiation with 600–800 MeV protons

Diffusional Interaction between U-10 wt.% Zr and Fe at 903K, 923K and 953K (630°C, 650°C, and 680°C)

Characterization of U-Pu-Zr and U-Pu-Mo Fuel Alloys in Transmission Electron Microscope

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