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Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys

Journal of nuclear materials, 2014-05, Vol.448 (1-3), p.96-102

2014

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Cr segregation on dislocation loops enhances hardening in ferritic Fe–Cr alloys

Acta materialia, 2013-03, Vol.61 (5), p.1444-1453

2013

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Ion irradiation combined with nanoindentation as a screening test procedure for irradiation hardening

Journal of nuclear materials, 2016-04, Vol.472, p.196-205

2016

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Helium-ion microscopy, helium-ion irradiation and nanoindentation of Eurofer 97 and ODS Eurofer

Journal of nuclear materials, 2018-07, Vol.505, p.267-275

2018

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Nanoindentation of single- (Fe) and dual-beam (Fe and He) ion-irradiated ODS Fe-14Cr-based alloys: Effect of the initial microstructure on irradiation-induced hardening

Journal of nuclear materials, 2019-05, Vol.518, p.1-10

2019

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Estimation of the solubility limit of Cr in Fe at 300 °C from small-angle neutron scattering in neutron-irradiated Fe–Cr alloys

Scripta materialia, 2009-12, Vol.61 (11), p.1060-1063

2009

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Microstructure characterization and strengthening mechanisms of oxide dispersion strengthened (ODS) Fe-9%Cr and Fe-14%Cr extruded bars

Journal of nuclear materials, 2017-11, Vol.495, p.6-19

2017

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Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels

Nuclear materials and energy, 2021-03, Vol.26, p.100918, Article 100918

2021

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Fabrication and characterization of oxide dispersion strengthened (ODS) 14Cr steels consolidated by means of hot isostatic pressing, hot extrusion and spark plasma sintering

Journal of nuclear materials, 2016-04, Vol.472, p.206-214

2016

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Contributions of Cu-rich clusters, dislocation loops and nanovoids to the irradiation-induced hardening of Cu-bearing low-Ni reactor pressure vessel steels

Journal of nuclear materials, 2015-06, Vol.461, p.37-44

2015

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Effect of anisotropic microstructure of ODS steels on small punch test results

Theoretical and applied fracture mechanics, 2019-04, Vol.100, p.191-199

2019

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Microstructural characterization of inhomogeneity in 9Cr ODS EUROFER steel

Journal of nuclear materials, 2020-05, Vol.533, p.152083, Article 152083

2020

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On the correlation between irradiation-induced microstructural features and the hardening of reactor pressure vessel steels

Journal of nuclear materials, 2010-11, Vol.406 (1), p.84-89

2010

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Ion-irradiation-induced damage in Fe–Cr alloys characterized by nanoindentation

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.980-983

2011

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Microstructure and fracture toughness characterization of three 9Cr ODS EUROFER steels with different thermo-mechanical treatments

Journal of nuclear materials, 2020-12, Vol.542, p.152464, Article 152464

2020

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Effect of neutron flux on the characteristics of irradiation-induced nanofeatures and hardening in pressure vessel steels

Acta materialia, 2016-02, Vol.104, p.131-142

2016

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Critical assessment of Cr-rich precipitates in neutron-irradiated Fe-12 at%Cr: Comparison of SANS and APT

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.463-469

2013

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Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses

Journal of nuclear materials, 2010-11, Vol.406 (1), p.73-83

2010

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Comparative small-angle neutron scattering study of neutron-irradiated Fe, Fe-based alloys and a pressure vessel steel

Journal of nuclear materials, 2010-04, Vol.399 (2), p.129-136

2010

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The microstructure of neutron-irradiated Fe–Cr alloys: A small-angle neutron scattering study

Journal of nuclear materials, 2011-02, Vol.409 (2), p.106-111

2011

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Microstructure-informed prediction and measurement of nanoindentation hardness of an Fe-9Cr alloy irradiated with Fe-ions of 1 and 5 MeV energy

Nuclear materials and energy, 2022-03, Vol.30, p.101105, Article 101105

2022

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Small-angle neutron scattering study of neutron-irradiated and post-irradiation annealed VVER-1000 reactor pressure vessel weld material

Frontiers in nuclear engineering, 2023-04, Vol.2

2023

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Small-angle neutron scattering of low-Cu RPV steels neutron-irradiated at 255°C and post-irradiation annealed at 290°C

Journal of nuclear materials, 2013-10, Vol.441 (1-3), p.487-492

2013

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Post-irradiation annealing behavior of neutron-irradiated FeCu, FeMnNi and FeMnNiCu model alloys investigated by means of small-angle neutron scattering

Journal of nuclear materials, 2014-11, Vol.454 (1-3), p.22-27

2014

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The dominant mechanisms for the formation of solute-rich clusters in low-Cu steels under irradiation

Materials today energy, 2020-09, Vol.17, p.100472, Article 100472

2020

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Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys

Cr segregation on dislocation loops enhances hardening in ferritic Fe–Cr alloys

Ion irradiation combined with nanoindentation as a screening test procedure for irradiation hardening

Helium-ion microscopy, helium-ion irradiation and nanoindentation of Eurofer 97 and ODS Eurofer

Nanoindentation of single- (Fe) and dual-beam (Fe and He) ion-irradiated ODS Fe-14Cr-based alloys: Effect of the initial microstructure on irradiation-induced hardening

Estimation of the solubility limit of Cr in Fe at 300 °C from small-angle neutron scattering in neutron-irradiated Fe–Cr alloys

Microstructure characterization and strengthening mechanisms of oxide dispersion strengthened (ODS) Fe-9%Cr and Fe-14%Cr extruded bars

Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels

Fabrication and characterization of oxide dispersion strengthened (ODS) 14Cr steels consolidated by means of hot isostatic pressing, hot extrusion and spark plasma sintering

Contributions of Cu-rich clusters, dislocation loops and nanovoids to the irradiation-induced hardening of Cu-bearing low-Ni reactor pressure vessel steels

Effect of anisotropic microstructure of ODS steels on small punch test results

Microstructural characterization of inhomogeneity in 9Cr ODS EUROFER steel

On the correlation between irradiation-induced microstructural features and the hardening of reactor pressure vessel steels

Ion-irradiation-induced damage in Fe–Cr alloys characterized by nanoindentation

Microstructure and fracture toughness characterization of three 9Cr ODS EUROFER steels with different thermo-mechanical treatments

Effect of neutron flux on the characteristics of irradiation-induced nanofeatures and hardening in pressure vessel steels

Critical assessment of Cr-rich precipitates in neutron-irradiated Fe-12 at%Cr: Comparison of SANS and APT

Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses

Comparative small-angle neutron scattering study of neutron-irradiated Fe, Fe-based alloys and a pressure vessel steel

The microstructure of neutron-irradiated Fe–Cr alloys: A small-angle neutron scattering study

Microstructure-informed prediction and measurement of nanoindentation hardness of an Fe-9Cr alloy irradiated with Fe-ions of 1 and 5 MeV energy

Small-angle neutron scattering study of neutron-irradiated and post-irradiation annealed VVER-1000 reactor pressure vessel weld material

Small-angle neutron scattering of low-Cu RPV steels neutron-irradiated at 255°C and post-irradiation annealed at 290°C

Post-irradiation annealing behavior of neutron-irradiated FeCu, FeMnNi and FeMnNiCu model alloys investigated by means of small-angle neutron scattering

The dominant mechanisms for the formation of solute-rich clusters in low-Cu steels under irradiation

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