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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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Radiation instability of equal channel angular extruded T91 at ultra-high damage levels

Acta materialia, 2017-06, Vol.132 (C), p.395-404

2017

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Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces

Acta materialia, 2016-09, Vol.116 (C), p.29-42

2016

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Accelerated materials evaluation for nuclear applications

Journal of nuclear materials, 2017-05, Vol.488 (C), p.46-62

2017

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Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation

Journal of nuclear materials, 2015-12, Vol.467 (Part 1), p.42-49

2015

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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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Modeling injected interstitial effects on void swelling in self-ion irradiation experiments

Journal of nuclear materials, 2016-04, Vol.471, p.200-207

2016

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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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Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations

Journal of nuclear materials, 2017-04, Vol.486 (C), p.86-95

2017

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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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Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8–12% Cr ferritic-martensitic steels

Journal of nuclear materials, 2016-01, Vol.468, p.264-273

2016

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Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions

Journal of nuclear materials, 2017-04, Vol.487 (C), p.96-104

2017

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Microstructural characterization and density change of 304 stainless steel reflector blocks after long-term irradiation in EBR-II

Journal of nuclear materials, 2015-10, Vol.465, p.516-530

2015

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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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Development of a nondestructive inspection method for irradiation-induced microstructural evolution of thick 304 stainless steel blocks

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.500-507

2013

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Retention of hydrogen in fcc metals irradiated at temperatures leading to high densities of bubbles or voids

Journal of nuclear materials, 2006-09, Vol.356 (1), p.122-135

2006

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Swelling of pure vanadium and V-5Cr at ∼430°C in response to variations in neutron flux-spectra in FFTF

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.314-318

2011

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Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II

Journal of nuclear materials, 2011-06, Vol.413 (1), p.53-61

2011

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Precipitate evolution in low-nickel austenitic stainless steels during neutron irradiation at very low dose rates

Journal of nuclear materials, 2009-04, Vol.386, p.661-665

2009

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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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Swelling of safety rod guide tubes in nonuniform fields of temperature and irradiation

Nuclear energy and technology, 2015-10, Vol.1 (2), p.88-92

2015

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Corrigendum to ‘Modeling injected interstitial effects on void swelling in self-ion irradiation experiments’ [Journal of Nuclear Materials 471 (2016) 200 – 207]

Journal of nuclear materials, 2023-04, Vol.576, p.154253, Article 154253

2023

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The synergistic influence of temperature and displacement rate on microstructural evolution of ion-irradiated Fe–15Cr–16Ni model austenitic alloy

Journal of nuclear materials, 2007-08, Vol.367, p.930-934

2007

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Influence of silicon on swelling and microstructure in Russian austenitic stainless steel EI-847 irradiated to high neutron doses

Journal of nuclear materials, 2008-08, Vol.378 (1), p.17-24

2008

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Mechanical properties of high-nickel alloys EP-753 and РЕ-16 after neutron irradiation to 54 dpa at 400–650 °С

Journal of nuclear materials, 2011-05, Vol.412 (1), p.30-34

2011

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On the use of SRIM for computing radiation damage exposure

Radiation instability of equal channel angular extruded T91 at ultra-high damage levels

Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent interfaces

Accelerated materials evaluation for nuclear applications

Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation

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

Modeling injected interstitial effects on void swelling in self-ion irradiation experiments

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

Stability of nanosized oxides in ferrite under extremely high dose self ion irradiations

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

Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8–12% Cr ferritic-martensitic steels

Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions

Microstructural characterization and density change of 304 stainless steel reflector blocks after long-term irradiation in EBR-II

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

Development of a nondestructive inspection method for irradiation-induced microstructural evolution of thick 304 stainless steel blocks

Retention of hydrogen in fcc metals irradiated at temperatures leading to high densities of bubbles or voids

Swelling of pure vanadium and V-5Cr at ∼430°C in response to variations in neutron flux-spectra in FFTF

Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II

Precipitate evolution in low-nickel austenitic stainless steels during neutron irradiation at very low dose rates

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

Swelling of safety rod guide tubes in nonuniform fields of temperature and irradiation

Corrigendum to ‘Modeling injected interstitial effects on void swelling in self-ion irradiation experiments’ [Journal of Nuclear Materials 471 (2016) 200 – 207]

The synergistic influence of temperature and displacement rate on microstructural evolution of ion-irradiated Fe–15Cr–16Ni model austenitic alloy

Influence of silicon on swelling and microstructure in Russian austenitic stainless steel EI-847 irradiated to high neutron doses

Mechanical properties of high-nickel alloys EP-753 and РЕ-16 after neutron irradiation to 54 dpa at 400–650 °С

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