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On the use of SRIM for computing radiation damage exposure

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2013-09, Vol.310, p.75-80

2013

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Grain boundary selective oxidation and intergranular stress corrosion crack growth of high-purity nickel binary alloys in high-temperature hydrogenated water

Corrosion science, 2018-02, Vol.131 (C), p.310-323

2018

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Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa

Journal of nuclear materials, 2014-10, Vol.453 (1-3), p.323-333

2014

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Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Journal of nuclear materials, 2016-12, Vol.482 (C), p.257-265

2016

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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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Irradiation creep and swelling from 400 to 600 °C of the oxide dispersion strengthened ferritic alloy MA957

Journal of nuclear materials, 2004-08, Vol.329, p.352-355

2004

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Shear punch tests performed using a new low compliance test fixture

Journal of nuclear materials, 2002-12, Vol.307, p.1619-1623

2002

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Comparison of fission neutron and proton/spallation neutron irradiation effects on the tensile behavior of type 316 and 304 stainless steel

Journal of nuclear materials, 2003-05, Vol.318 (Complete), p.283-291

2003

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Ductility correlations between shear punch and uniaxial tensile test data

Journal of nuclear materials, 2000-12, Vol.283, p.987-991

2000

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Erratum to “On the use of SRIM for computing radiation damage exposure” [Nucl. Instrum. Methods Phys. Res. B 310 (2013) 75–80]

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2019-11, Vol.459, p.196-197

2019

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Linking Grain Boundary Microstructure to Stress Corrosion Cracking of Cold-Rolled Alloy 690 in Pressurized Water Reactor Primary Water

Corrosion (Houston, Tex.), 2013-10, Vol.69 (10), p.953-963

2013

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Validation of the shear punch–tensile correlation technique using irradiated materials

Journal of nuclear materials, 1998-10, Vol.258, p.1651-1656

1998

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International Round-Robin on Stress Corrosion Crack Initiation of Alloy 600 Material in Pressurized Water Reactor Primary Water

Corrosion (Houston, Tex.), 2020-08, Vol.76 (8), p.719-733

2020

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Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40–110dpa at 400–750°C in FFTF

Journal of nuclear materials, 2012-09, Vol.428 (1-3), p.170-175

2012

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The effect of 800MeV proton irradiation on the mechanical properties of tungsten at room temperature and at 475°C

Journal of nuclear materials, 2005-08, Vol.343 (1-3), p.219-226

2005

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Analysis of possible deformation mechanisms in helium–ion irradiated SiC

Journal of nuclear materials, 2002-12, Vol.307, p.1178-1182

2002

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Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500dpa

Journal of nuclear materials, 2014-10, Vol.453 (1-3), p.323-333

2014

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Irradiation creep of various ferritic alloys irradiated at ∼400°C in the PFR and FFTF reactors

Journal of nuclear materials, 1998-10, Vol.258, p.1163-1166

1998

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Shear punch testing of candidate reactor materials after irradiation in fast reactors and spallation environments

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.1005-1008

2011

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SANS and TEM of ferritic–martensitic steel T91 irradiated in FFTF up to 184dpa at 413°C

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.91-97

2013

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The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels

Journal of nuclear materials, 2006-09, Vol.356 (1), p.62-69

2006

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Hierarchical microstructures in CZT

Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment, 2011-10, Vol.652 (1), p.174-177

2011

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High temperature tensile testing of modified 9Cr–1Mo after irradiation with high energy protons

Journal of nuclear materials, 2003-05, Vol.318 (Complete), p.200-206

2003

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Thermal creep mechanisms in V–4Cr–4Ti pressurized tube specimens

Journal of nuclear materials, 2007-08, Vol.367, p.869-875

2007

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Determination of the creep compliance and creep-swelling coupling coefficient for neutron irradiated titanium-modified stainless steels at ∼ 400°C

Journal of nuclear materials, 1992-09, Vol.191, p.803-807

1992

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On the use of SRIM for computing radiation damage exposure

Grain boundary selective oxidation and intergranular stress corrosion crack growth of high-purity nickel binary alloys in high-temperature hydrogenated water

Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

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

Irradiation creep and swelling from 400 to 600 °C of the oxide dispersion strengthened ferritic alloy MA957

Shear punch tests performed using a new low compliance test fixture

Comparison of fission neutron and proton/spallation neutron irradiation effects on the tensile behavior of type 316 and 304 stainless steel

Ductility correlations between shear punch and uniaxial tensile test data

Erratum to “On the use of SRIM for computing radiation damage exposure” [Nucl. Instrum. Methods Phys. Res. B 310 (2013) 75–80]

Linking Grain Boundary Microstructure to Stress Corrosion Cracking of Cold-Rolled Alloy 690 in Pressurized Water Reactor Primary Water

Validation of the shear punch–tensile correlation technique using irradiated materials

International Round-Robin on Stress Corrosion Crack Initiation of Alloy 600 Material in Pressurized Water Reactor Primary Water

Irradiation creep and density changes observed in MA957 pressurized tubes irradiated to doses of 40–110dpa at 400–750°C in FFTF

The effect of 800MeV proton irradiation on the mechanical properties of tungsten at room temperature and at 475°C

Analysis of possible deformation mechanisms in helium–ion irradiated SiC

Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500dpa

Irradiation creep of various ferritic alloys irradiated at ∼400°C in the PFR and FFTF reactors

Shear punch testing of candidate reactor materials after irradiation in fast reactors and spallation environments

SANS and TEM of ferritic–martensitic steel T91 irradiated in FFTF up to 184dpa at 413°C

The effects of fast reactor irradiation conditions on the tensile properties of two ferritic/martensitic steels

Hierarchical microstructures in CZT

High temperature tensile testing of modified 9Cr–1Mo after irradiation with high energy protons

Thermal creep mechanisms in V–4Cr–4Ti pressurized tube specimens

Determination of the creep compliance and creep-swelling coupling coefficient for neutron irradiated titanium-modified stainless steels at ∼ 400°C

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