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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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Loyer-Prost, Marie
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (14/14 displayed)
- 2025Influence of injected ions on α’ formation under ion irradiation in Oxide Dispersion Strengthened Steelscitations
- 2024Accurate quantification of dislocation loops in complex functional alloys enabled by deep learning image analysiscitations
- 2023On the use of nanoscale multilayers to determine interdiffusion coefficients: comprehensive characterization of interdiffusion at low temperature in theNi-Cr systemcitations
- 2023Compact A15 Frank-Kasper nano-phases at the origin of dislocation loops in face-centred cubic metalscitations
- 2023Impact of micro-alloying in ion-irradiated nickel: From the inhibition of point-defect cluster diffusion by thermal segregation to the change of dislocation loop naturecitations
- 2023Impact of intragranular misorientation on void swelling and inter-granular cavities after ion irradiation in standard and additive manufacturing 316 L austenitic steelscitations
- 2022Effect of grain boundary planes on radiation-induced segregation (RIS) at near Σ3 grain boundaries in Fe-Cr alloy under ion irradiationcitations
- 2022Impact of the local microstructure fluctuations on radiation-induced segregation in dilute Fe-Ni and Ni-Ti model alloys: a combined modeling and experimental analysiscitations
- 2022Radiation-induced sharpening in Cr-Coated zirconium alloycitations
- 2021Impact of ion and neutron irradiation on the corrosion of the 6061-T6 aluminium alloy ; Influence de l'irradiation par ions et neutrons sur la corrosion de l'alliage d'aluminium 6061-T6citations
- 2021Impact of the microstructure on the swelling of aluminum alloys: characterization and modelling basescitations
- 2021Thermodynamic model for lattice point defect-mediated semi-coherent precipitation in alloyscitations
- 2021Nano-Structured Materials under Irradiation: Oxide Dispersion-Strengthened Steelscitations
- 2021Impact of ion and neutron irradiation on the corrosion of the 6061-T6 aluminium alloycitations
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article
Impact of the microstructure on the swelling of aluminum alloys: characterization and modelling bases
Abstract
Swelling of metals under irradiation is largely studied in the nuclear industry for its impact on the safe and efficient operation of reactors. However, the case of aluminum alloys remains poorly documented as they are exclusively used in nuclear research reactors which operate at lower temperatures than nuclear power plants. Void swelling in aluminum alloys, which results from the cavities induced by the fast neutron flux in reactor, is measurable only at high fluences, for which few measurement points are available. In this study, samples with various quenching rates were used in order to simulate the variations obtainable during the fabrication of large reactor components. A first series of samples were irradiated with heavy ions in single beam (Au$^4+$) to understand the impact of the quenched microstructure on the voids swelling. A second series of samples were irradiated in a triple beam (W$^9+$, He$^+$ and Si$^+$) to simulate the aluminum transmutation occurring inside reactors. Samples were investigated at very fine scale and characterized to understand the key mechanisms of swelling. Then, quantitative measurements of the swelling were performed in each sample. A high dispersion of the swelling values and a higher value are observed after ion irradiation compared to neutron irradiation for a similar irradiation dose, which seems to be related to the very high damage rate created by ion-irradiation. The high dispersion of published swelling values measured after neutron irradiation is interpreted as due to different neutron spectrum conditions because of different positions of the samples in the reactors. Therefore, it appears relevant to complement the description of swelling in aluminum alloys with a modeling approach. Swelling values from the literature were incorporated into a Brailsford & Bullough swelling model for two different damage rates, after estimating the parameters of the model from the literature. This work aims at a better comprehension of the swelling of aluminum alloys both from a quantitative and qualitative point of view and draws the basics requirements for future swelling models.