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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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Magnetic phase formation in irradiated austenitic alloys

Journal of nuclear materials, 2014-05, Vol.448 (1-3), p.294-300

2014

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Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa

Journal of nuclear materials, 2009-02, Vol.384 (3), p.249-255

2009

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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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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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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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Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30―60 years

Journal of nuclear materials, 2013-06, Vol.437 (1-3), p.415-423

2013

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Effects of dpa rate on swelling in neutron-irradiated Fe–Cr and Fe–Cr–Mo alloys

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.944-948

2011

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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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Microstructural defect evolution in neutron – Irradiated 12Cr18Ni9Ti stainless steel during subsequent isochronous annealing

Journal of nuclear materials, 2013-08, Vol.439 (1-3), p.148-158

2013

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Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS

Journal of nuclear materials, 2003-04, Vol.317 (1), p.32-45

2003

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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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Prediction of swelling of 18Cr10NiTi austenitic steel over a wide range of displacement rates

Journal of nuclear materials, 2010-04, Vol.399 (1), p.114-121

2010

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Development of nondestructive inspection techniques for measurement of void swelling in irradiated microscopy disks

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.992-995

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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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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Neutron-induced swelling and embrittlement of pure iron and pure nickel irradiated in the BN-350 and BOR-60 fast reactors

Journal of nuclear materials, 2008-04, Vol.375 (3), p.359-364

2008

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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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Impact of nano-oxides and injected gas on swelling and hardening of 18Cr10NiTi stainless steel during ion irradiation

Journal of nuclear materials, 2022-07, Vol.565, p.153666, Article 153666

2022

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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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Displacement and helium-induced enhancement of hydrogen and deuterium retention in ion-irradiated 18Cr10NiTi stainless steel

Journal of nuclear materials, 2006-09, Vol.356 (1), p.136-147

2006

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High-dose neutron irradiation of MgAl2O4 spinel: effects of post-irradiation thermal annealing on EPR and optical absorption

Journal of nuclear materials, 2005-02, Vol.336 (2-3), p.156-162

2005

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Anisotropic swelling observed during stress-free reirradiation of AISI 304 tubes previously irradiated under stress

Journal of nuclear materials, 2009-04, Vol.386, p.249-253

2009

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

Magnetic phase formation in irradiated austenitic alloys

Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa

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

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

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

Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30―60 years

Effects of dpa rate on swelling in neutron-irradiated Fe–Cr and Fe–Cr–Mo alloys

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

Microstructural defect evolution in neutron – Irradiated 12Cr18Ni9Ti stainless steel during subsequent isochronous annealing

Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS

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

Prediction of swelling of 18Cr10NiTi austenitic steel over a wide range of displacement rates

Development of nondestructive inspection techniques for measurement of void swelling in irradiated microscopy disks

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

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

Neutron-induced swelling and embrittlement of pure iron and pure nickel irradiated in the BN-350 and BOR-60 fast reactors

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

Impact of nano-oxides and injected gas on swelling and hardening of 18Cr10NiTi stainless steel during ion irradiation

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

Displacement and helium-induced enhancement of hydrogen and deuterium retention in ion-irradiated 18Cr10NiTi stainless steel

High-dose neutron irradiation of MgAl2O4 spinel: effects of post-irradiation thermal annealing on EPR and optical absorption

Anisotropic swelling observed during stress-free reirradiation of AISI 304 tubes previously irradiated under stress

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