| People | Locations | Statistics |
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| Naji, M. |
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| Motta, Antonella |
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| Aletan, Dirar |
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| Mohamed, Tarek |
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| Ertürk, Emre |
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| Taccardi, Nicola |
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| Kononenko, Denys |
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| Petrov, R. H. | Madrid |
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| Alshaaer, Mazen | Brussels |
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| Bih, L. |
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| Casati, R. |
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| Muller, Hermance |
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| Kočí, Jan | Prague |
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| Šuljagić, Marija |
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| Kalteremidou, Kalliopi-Artemi | Brussels |
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| Azam, Siraj |
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| Ospanova, Alyiya |
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| Blanpain, Bart |
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| Ali, M. A. |
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| Popa, V. |
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| Rančić, M. |
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| Ollier, Nadège |
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| Azevedo, Nuno Monteiro |
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| Landes, Michael |
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| Rignanese, Gian-Marco |
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Pareige, Cristelle
University of Rouen
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (24/24 displayed)
- 2024On the iron content of Mn-Ni-Si-rich clusters that form in reactor pressure vessel steels during exposure to neutron irradiationcitations
- 2024Multiscale Characterisation Study on the Effect of Heat Treatment on the Microstructure of Additively Manufactured 316L Stainless Steelcitations
- 2023Reconciliation between simulated and measured microstructures of metastable FeCr alloys: A phase field approachcitations
- 2022Surface Modification of 304L Stainless Steel and Interface Engineering by HiPIMS Pre-Treatmentcitations
- 2022Phase instabilities in austenitic steels during particle bombardment at high and low dose rates qcitations
- 2022Effect of grain boundary planes on radiation-induced segregation (RIS) at near Σ3 grain boundaries in Fe-Cr alloy under ion irradiationcitations
- 2021Effect of Ni, Mo and Mn content on spinodal decomposition kinetics and G-phase precipitation of aged model cast austenitic stainless steels.citations
- 2021Effect of Ni, Mo and Mn content on spinodal decomposition kinetics and G-phase precipitation of aged model cast austenitic stainless steelscitations
- 2020Nano-hardening features in high-dose neutron irradiated Eurofer97 revealed by atom-probe tomographycitations
- 2020Microstructure influence on creep properties of heat-resistant austenitic alloys with high aluminum contentcitations
- 2020Effect of annealing treatment at 550 °C on ferrite of thermally aged cast austenitic stainless steels and ageing kinetics of reverted cast austenitic stainless steelscitations
- 2019Quantification of APT physical limitations on chemical composition of precipitates in Fe–Cr alloyscitations
- 2019On the role of Ni, Si and P on the nanostructural evolution of FeCr alloys under irradiationcitations
- 2015Kinetics of G-phase precipitation and spinodal decomposition in very long aged ferrite of a Mo-free duplex stainless steelcitations
- 2014Kinetics of secondary phase precipitation during spinodal decomposition in duplex stainless steels: A kinetic Monte Carlo model – Comparison with atom probe tomography experimentscitations
- 2014Nano-scale study of phase separation in ferrite of long term thermally aged Mo-beaaring duplex stainless steels - atom probe tomography and Monte Carlo Simulation
- 2014Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high-purity Fe-Cr alloyscitations
- 2013Characterisation of Cr, Si and P distribution at dislocations and grain-boundaries in neutron irradiated Fe–Cr model alloys of low puritycitations
- 2013Cr precipitation in neutron irradiated industrial purity Fe–Cr model alloyscitations
- 2012Crystallisation and molecular mobilities in liquid and glassy states of a MXD6 polyamidecitations
- 2011Effect of neutron-irradiation on the microstructure of a Fe–12at.%Cr alloycitations
- 2011Study of phase transformation and mechanical properties evolution of duplex stainless steels after long term thermal ageing (>20years)citations
- 2010Atomic scale study of phase transformation in long term thermally aged duplex stainless steels: relation between microstructure and properties
- 2007Phase transformation and segregation to lattice defects in Ni-base superalloyscitations
Places of action
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article
Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high-purity Fe-Cr alloys
Abstract
Reduced activation high-chromium ferritic/martensitic steels are candidate materials for Generation IV fission and fusion reactors. To gain knowledge about the radiation resistance of these steels in such environments, the first step is to study the Fe-Cr matrix of this material. For that purpose and to understand ballistic damage by neutrons, self-ion irradiations, with and without simultaneous He injection, were performed on a series of high-purity Fe-Cr binary alloys at 773 K. Transmission electron microscopy (TEM) analysis revealed "displacement fringe contrast" inside the dislocation loops. This was attributed to the presence of Cr-enriched zones on their habit plane, which is a defect-free region for body-centered cubic Fe-based alloys. A plausible mechanism is discussed to explain the phenomenon, the first step of which would be the radiation-induced segregation of Cr atoms on the dislocation loop core. Energy-dispersive X-ray spectroscopy in scanning TEM mode and atom probe tomography (APT) gave a coherent quantitative estimate of the Cr concentration in these enriched areas. APT study showed that the enrichment was heterogeneous on the loop plane. Upon in situ annealing up to 900 K, the loops and the fringes disappeared completely, without leaving a secondary-phase particle, such as carbide, at their position. Fringes were present until the loop disappeared.