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Dislocation-oxide interaction in Y2O3 embedded Fe: A molecular dynamics simulation study
- Source :
- Nuclear Engineering and Technology, Vol 52, Iss 2, Pp 337-343 (2020)
- Publication Year :
- 2020
- Publisher :
- Elsevier BV, 2020.
-
Abstract
- Oxide dispersed strengthened (ODS) steel is an important candidate for Gen-IV reactors. Oxide embedded in Fe can help to trap irradiation defects and enhances the strength of steel. It was observed in this study that the size of oxide has a profound impact on the depinning mechanism. For smaller sizes, the oxide acts as a void; thus, letting the dislocation bypass without any shear. On the other hand, oxides larger than 2 nm generate new dislocation segments around themselves. The depinning is similar to that of Orowan mechanism and the strengthening effect is likely to be greater for larger oxides. It was found that higher shear deformation rates produce more fine-tuned stress-strain curve. Both molecular dynamics (MD) simulations and BKS (Bacon-Knocks-Scattergood) model display similar characteristics whereby establishing an inverse relation between the depinning stress and the obstacle distance. It was found that (110)oxide || (111)Fe (oriented oxide) also had similar characteristics as that of (100)oxide || (111)Fe but resulted in an increased depinning stress thereby providing greater resistance to dislocation bypass. Our simulation results concluded that critical depinning stress depends significantly on the size and orientation of the oxide. Keywords: Oxide dispersed strengthened (ODS) steel, Molecular dynamics (MD) simulation, Edge dislocation, Orowan loop, Dislocation dynamics
- Subjects :
- Void (astronomy)
Materials science
020209 energy
Oxide
02 engineering and technology
lcsh:TK9001-9401
030218 nuclear medicine & medical imaging
03 medical and health sciences
chemistry.chemical_compound
Molecular dynamics
0302 clinical medicine
Nuclear Energy and Engineering
chemistry
0202 electrical engineering, electronic engineering, information engineering
lcsh:Nuclear engineering. Atomic power
Irradiation
Composite material
Subjects
Details
- ISSN :
- 17385733
- Volume :
- 52
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Technology
- Accession number :
- edsair.doi.dedup.....dd0a107251ba0cbee6b30563c6771cd2