Vincent et al., 2008 - Google Patents
Precipitation of the FeCu system: A critical review of atomic kinetic Monte Carlo simulationsVincent et al., 2008
View HTML- Document ID
- 17651390332704797635
- Author
- Vincent E
- Becquart C
- Pareige C
- Pareige P
- Domain C
- Publication year
- Publication venue
- Journal of Nuclear Materials
External Links
Snippet
Cu is of primary importance in the embrittlement of the neutron-irradiated reactor pressure vessel (RPV) steels. It has been observed to segregate into copper-rich precipitates within the ferrite matrix under irradiation. Since its role was discovered more than 40 years ago, Cu …
- 238000001556 precipitation 0 title abstract description 48
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Vincent et al. | Precipitation of the FeCu system: A critical review of atomic kinetic Monte Carlo simulations | |
| Vincent et al. | Solute interaction with point defects in α Fe during thermal ageing: A combined ab initio and atomic kinetic Monte Carlo approach | |
| Fu et al. | Ab initio study of helium in α-Fe: Dissolution, migration, and clustering with vacancies | |
| Domain et al. | Simulation of radiation damage in Fe alloys: an object kinetic Monte Carlo approach | |
| Mamivand et al. | CuMnNiSi precipitate evolution in irradiated reactor pressure vessel steels: Integrated Cluster Dynamics and experiments | |
| Soneda et al. | Modeling the microstructural evolution in bcc-Fe during irradiation using kinetic Monte Carlo computer simulation | |
| Bai et al. | Modeling copper precipitation hardening and embrittlement in a dilute Fe-0.3 at.% Cu alloy under neutron irradiation | |
| Wirth et al. | Modeling defect cluster evolution in irradiated structural materials: Focus on comparing to high-resolution experimental characterization studies | |
| Becquart et al. | Modeling the long-term evolution of the primary damage in ferritic alloys using coarse-grained methods | |
| Hu et al. | Modeling of irradiation hardening of iron after low-dose and low-temperature neutron irradiation | |
| Vincent et al. | Microstructural evolution under high flux irradiation of dilute Fe–CuNiMnSi alloys studied by an atomic kinetic Monte Carlo model accounting for both vacancies and self interstitials | |
| Martinez et al. | Cr interactions with He and vacancies in dilute Fe-Cr alloys from first principles | |
| Badillo et al. | A phase field model for segregation and precipitation induced by irradiation in alloys | |
| Vincent et al. | Atomic kinetic Monte Carlo model based on ab initio data: Simulation of microstructural evolution under irradiation of dilute Fe–CuNiMnSi alloys | |
| Balbuena et al. | An object kinetic Monte Carlo method to model precipitation and segregation in alloys under irradiation | |
| Yu et al. | Dislocation loop bias and void swelling in irradiated α-iron from mesoscale and atomistic simulations | |
| Insepov et al. | Derivation of kinetic coefficients by atomistic methods for studying defect behavior in Mo | |
| Yüksel et al. | Low-energy quadrupole states in neutron-rich tin nuclei | |
| Bonny et al. | Kinetic Monte Carlo model for 1-D migration in a field of strong traps: Application to self-interstitial clusters in W-Re alloys | |
| Sarriguren | Weak interaction rates for Kr and Sr waiting-point nuclei under rp-process conditions | |
| Osetsky et al. | On the mobility of defect clusters and their effect on microstructure evolution in fcc Ni under irradiation | |
| Samaras et al. | Modelling in nuclear energy environments | |
| Chen et al. | MD simulation of the He bubble effect on H retention in BCC iron | |
| Vizoso et al. | The effects of dose, dose rate, and irradiation type and their equivalence on radiation-induced segregation in binary alloy systems via phase-field simulations | |
| Ngayam-Happy et al. | Isochronal annealing of electron-irradiated dilute Fe alloys modelled by an ab initio based AKMC method: Influence of solute–interstitial cluster properties |