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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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Henry, J.
Royal Academy of Engineering
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (21/21 displayed)
- 2021Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technology
- 2021Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technologycitations
- 2021Impact of materials technology on the breeding blanket design – Recent progress and case studies in materials technologycitations
- 2021Technological aspects in blanket design: Effects of micro-alloying and thermo-mechanical treatments of EUROFER97 type steels after neutron irradiation
- 2021Development of RAFM steel for nuclear applications with reduced manganese, silicon and carbon contentcitations
- 2021Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditionscitations
- 2021Fabrication routes for advanced first wall design alternatives
- 2021Fabrication routes for advanced first wall design alternativescitations
- 2020Bio-inspired non-self-similar hierarchical microstructures for damage tolerancecitations
- 2018Thermally Deposited Sb2S3: Bi Thin Films for Solar Cell Absorbercitations
- 2018Radiation-induced bcc-fcc phase transformation in a Fe-3%Ni alloycitations
- 2018Radiation-induced bcc-fcc phase transformation in a Fe-3percentNi alloy
- 2017Virtual testing framework for hybrid aligned discontinuous compositescitations
- 2016Effect of chromium on void swelling in ion irradiated high purity Fe–Cr alloyscitations
- 2016Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature servicecitations
- 2014Chromium enrichment on the habit plane of dislocation loops in ion-irradiated high-purity Fe-Cr alloyscitations
- 2013He and Cr effects on radiation damage formation in ion-irradiated pure iron and Fe-5.40 wt.% Cr: A transmission electron microscopy studycitations
- 2013Single- and dual-beam in situ irradiations of high-purity iron in a transmission electron microscope: Effects of heavy ion irradiation and helium injectioncitations
- 2011Dual-beam irradiation of α-iron: Heterogeneous bubble formation on dislocation loopscitations
- 2008Tensile behaviour of 9Cr–1Mo tempered martensitic steels irradiated up to 20 dpa in a spallation environmentcitations
- 2006Assessment of the lifetime of the beam window of the MEGAPIE target liquid metal container
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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.