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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-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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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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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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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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Nanoscale characterization of ODS Fe–9%Cr model alloys compacted by spark plasma sintering

Journal of nuclear materials, 2012-09, Vol.428 (1-3), p.139-146

2012

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Microstructure of oxide dispersion strengthened Eurofer and iron–chromium alloys investigated by means of small-angle neutron scattering and transmission electron microscopy

Journal of nuclear materials, 2011-09, Vol.416 (1), p.35-39

2011

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Flux dependence of cluster formation in neutron-irradiated weld material

Journal of physics. Condensed matter, 2008-03, Vol.20 (10), p.104262

2008

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Nanoclusters in bcc-Fe containing vacancies, copper and nickel: Structure and energetics

Journal of nuclear materials, 2011-11, Vol.418 (1), p.215-222

2011

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SANS investigation of a neutron-irradiated Fe–9 at%Cr alloy

Journal of nuclear materials, 2010-12, Vol.407 (1), p.29-33

2010

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Structure, energetics and thermodynamics of copper–vacancy clusters in bcc-Fe: An atomistic study

Journal of nuclear materials, 2011-07, Vol.414 (2), p.161-168

2011

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A new approach to the correlation between the coefficient and the exponent in the power law equation of fatigue crack growth

International journal of fatigue, 2000-03, Vol.22 (3), p.229-239

2000

Volltextzugriff (PDF)

Small-angle neutron scattering study of neutron-irradiated iron and an iron–nickel alloy

Journal of nuclear materials, 2008-02, Vol.374 (1), p.334-337

2008

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Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned reactor

Journal of nuclear materials, 2011-09, Vol.416 (1), p.111-116

2011

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On the factors affecting the propagation of long fatigue cracks in thin-sheet wrought aluminium alloys

International journal of fatigue, 2003-09, Vol.25 (9), p.885-889

2003

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The material-dependent variability of fatigue crack growth rates of aluminium alloys in the Paris regime

International journal of fatigue, 2001-05, Vol.23 (5), p.383-394

2001

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Mapping of the rate-controlling steps for environment-assisted fatigue crack growth applied to the aluminium alloy 6013 T6

International journal of fatigue, 2002-08, Vol.24 (8), p.831-839

2002

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Scaling of self-similar long fatigue crack growth in aluminium alloys

Materials science & engineering. A, Structural materials : properties, microstructure and processing, 2005, Vol.400-01, p.422-425

BERGNER, F

2005

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Environment-sensitive fracture of aluminium alloy 6013

Materials and corrosion, 2000-09, Vol.51 (9), p.628-634

2000

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On the correlation between irradiation-induced microstructural features and the hardening of reactor pressure vessel steels: FP6 IP PERFECT Project: Prediction of Irradiation Damage Effects in Reactor Components

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

2010

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Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses: FP6 IP PERFECT Project: Prediction of Irradiation Damage Effects in Reactor Components

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

2010

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Critical assessment of Cr-rich precipitates in neutron-irradiated Fe―12 at%Cr: Comparison of SANS and APT : Development of New structural Materials for Advanced Fission and Fusion Reactor Systems

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

2013

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Influence of the depth position on the neutron embrittlement of the VVER reactor pressure vessel steel 15Cr2MoV(A) consequences for the assessment of reactor safety

Nuclear engineering and design, 1995-11, Vol.159 (2), p.131-141

1995

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The role of microstructure in the propagation of ultrasound in bainitic low-alloy steels

International journal of pressure vessels and piping, 1993, Vol.55 (2), p.251-260

1993

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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-induced damage in Fe–Cr alloys characterized by nanoindentation

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

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

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

Nanoscale characterization of ODS Fe–9%Cr model alloys compacted by spark plasma sintering

Microstructure of oxide dispersion strengthened Eurofer and iron–chromium alloys investigated by means of small-angle neutron scattering and transmission electron microscopy

Flux dependence of cluster formation in neutron-irradiated weld material

Nanoclusters in bcc-Fe containing vacancies, copper and nickel: Structure and energetics

SANS investigation of a neutron-irradiated Fe–9 at%Cr alloy

Structure, energetics and thermodynamics of copper–vacancy clusters in bcc-Fe: An atomistic study

A new approach to the correlation between the coefficient and the exponent in the power law equation of fatigue crack growth

Small-angle neutron scattering study of neutron-irradiated iron and an iron–nickel alloy

Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned reactor

On the factors affecting the propagation of long fatigue cracks in thin-sheet wrought aluminium alloys

The material-dependent variability of fatigue crack growth rates of aluminium alloys in the Paris regime

Mapping of the rate-controlling steps for environment-assisted fatigue crack growth applied to the aluminium alloy 6013 T6

Scaling of self-similar long fatigue crack growth in aluminium alloys

Environment-sensitive fracture of aluminium alloy 6013

On the correlation between irradiation-induced microstructural features and the hardening of reactor pressure vessel steels: FP6 IP PERFECT Project: Prediction of Irradiation Damage Effects in Reactor Components

Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses: FP6 IP PERFECT Project: Prediction of Irradiation Damage Effects in Reactor Components

Critical assessment of Cr-rich precipitates in neutron-irradiated Fe―12 at%Cr: Comparison of SANS and APT : Development of New structural Materials for Advanced Fission and Fusion Reactor Systems

Influence of the depth position on the neutron embrittlement of the VVER reactor pressure vessel steel 15Cr2MoV(A) consequences for the assessment of reactor safety

The role of microstructure in the propagation of ultrasound in bainitic low-alloy steels

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