A5008158631- Fusion materials and technologies
- Nuclear Materials and Properties
- Advanced Materials Characterization Techniques
- Ion-surface interactions and analysis
- Hydrogen embrittlement and corrosion behaviors in metals
- Microstructure and Mechanical Properties of Steels
- Silicon Carbide Semiconductor Technologies
- Advanced ceramic materials synthesis
- Metal Alloys Wear and Properties
- Nuclear materials and radiation effects
- Microstructure and mechanical properties
- High Temperature Alloys and Creep
- Electron and X-Ray Spectroscopy Techniques
- Intermetallics and Advanced Alloy Properties
- Metallurgical Processes and Thermodynamics
- X-ray Diffraction in Crystallography
- High Entropy Alloys Studies
- nanoparticles nucleation surface interactions
- Aluminum Alloy Microstructure Properties
- Material Properties and Applications
- Surface and Thin Film Phenomena
- Semiconductor materials and devices
- Diamond and Carbon-based Materials Research
- Advanced Physical and Chemical Molecular Interactions
- Semiconductor materials and interfaces
Université Paris-Saclay
2016-2024
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2014-2024
CEA Paris-Saclay
2010-2024
Direction des énergies
2011-2016
Groupe de Physique des Matériaux
2010
CEA Paris-Saclay - Etablissement de Saclay
2008
Depending on the particle used to irradiate Fe–Cr alloys, at same dose and temperature, α′ precipitation may occur or not. This paper aims explaining origin of absence under ion irradiation. A Fe–15at.%Cr alloy was irradiated with 2 MeV Fe2+ ions 300°C analysed using atom probe tomography. For first time our knowledge, particles were observed The characterisation α/α′ decomposition depth showed that injected Fe strongly reduced precipitation. They might have played a major role in
Carbon atoms are always present in Fe-based materials, either as impurities even high purity samples or an intrinsic constituent steels. Density Functional Theory calculations have been performed to study the interaction between C and vacancies (V) α-Fe. We find that formation of VCn complexes is energetically favourable for n ≤ 3, with VC2 being most stable one. The energy gain corresponding clustering reaction VCn-1 + → depends mainly on strength C-C covalent bonds. vacancy diffusivity...
By combining density functional theory, empirical potential, and atomic transport model approaches, we investigate the energetics diffusion properties of P interstitials in dilute $\mathrm{Fe}\text{\ensuremath{-}}\mathrm{P}$ alloys. Although is a substitutional impurity $\ensuremath{\alpha}$-iron, when self-interstitial atom (SIA) approaches P, becomes interstitial with an energy gain up to $1.0\phantom{\rule{0.3em}{0ex}}\mathrm{eV}$. The octahedral $⟨110⟩$ mixed dumbbell are lowest-energy...
The M4F project brings together the fusion and fission materials communities working on prediction of radiation damage production evolution their effects mechanical behaviour irradiated ferritic/martensitic (F/M) steels. It is a multidisciplinary in which several different experimental computational science tools are integrated to understand model complex phenomena associated with formation irradiation induced defects macroscopic target materials. In particular focuses two specific aspects:...
Self-ion irradiation of pure tungsten with 2 MeV W ions provides a way simulating microstructures generated by neutron in components fusion reactor. Transmission electron microscopy (TEM) has been used to characterize defects formed samples ion irradiation. It was found that irradiated 0.85 dpa at relatively low temperatures develops characteristic microstructure dominated dislocation loops and black dots. The density size distribution these were estimated. Some the exposed self-ion then...
Abstract The formation of precipitates with an atomic volume different from their parent phase eventually leads to a loss the lattice continuity at matrix–precipitate interface. Here, we show creation or removal sites mediated by point defects is accommodation mechanism coherency and even precipitation driving force. We introduce thermodynamic approach that rationalizes selection phases resulting chemical crystallographic constraints in relation defect properties. semi-coherent diagram...
Effect of helium on void swelling was studied in high-purity α-iron, irradiated using energetic self-ions to 157 displacements per atom (dpa) at 773 K, with and without co-implantation up 17 atomic parts-per-million (appm) He/dpa. Helium is known enhance cavity formation metals irradiation environments, leading early onset. In this study, microstructure characterization by transmission electron microscopy revealed compelling evidence dramatic reduction co-implantation, achieved primarily...