Results 11 to 20 of about 58,697 (194)

Atomistic study of internal stress effect on scratching behavior in titanium single crystal

open access: yesJournal of Materials Research and Technology, 2023
The internal stress effect on the scratching behavior in titanium single crystal is investigated by molecular dynamics simulations. It is introduced by applying the compressive/tensile pre-strain in this work.
Anshuo Xu   +5 more
doaj   +1 more source

Behavior of a self-interstitial-atom type dislocation loop in the periphery of an edge dislocation in BCC-Fe

open access: yesNuclear Materials and Energy, 2016
The behavior of the dislocation loop of a self-interstitial atom (SIA) near an edge dislocation and its conservative climb process were modeled in body-centered cubic Fe by incorporating loop rotation.
Sho Hayakawa   +5 more
doaj   +1 more source

Microstructural modifications in tungsten induced by high flux plasma exposure : TEM examination [PDF]

open access: yes, 2016
We have performed microstructural characterization using transmission electron microscopy (TEM) techniques to reveal nanometric features in the sub-surface region of tungsten samples exposed to high flux, low energy deuterium plasma.
Bakaeva, Anastasiia   +5 more
core   +1 more source

Effects of stacking fault energies on the interaction between an edge dislocation and an 8.0-nm-diameter Frank loop of self-interstitial atoms

open access: yesNuclear Materials and Energy, 2016
Molecular dynamics simulations were conducted to investigate the effects of stacking fault energy (SFE) as a single variable parameter on the interaction between an edge dislocation and a Frank loop of self-interstitial atoms with a diameter of 8.0nm ...
S. Hayakawa   +5 more
doaj   +1 more source

Dislocation Dynamics Model to Simulate Motion of Dislocation Loops in Metallic Materials

open access: yesMetals, 2022
Dislocation dynamics has been an intensive research subject in materials science and engineering due to the significant roles it plays in plastic deformation and the hardening of metals, fracture mechanics, and the fabrication of semiconductor thin films.
Xinze Tan, Enhui Tan, Lizhi Sun
doaj   +1 more source

Dislocation dynamics simulations with climb: kinetics of dislocation loop coarsening controlled by bulk diffusion [PDF]

open access: yes, 2011
Dislocation climb mobilities, assuming vacancy bulk diffusion, are derived and implemented in dislocation dynamics simulations to study the coarsening of vacancy prismatic loops in fcc metals.
Bakó, Botond   +3 more
core   +7 more sources

Global transition path search for dislocation formation in Ge on Si(001) [PDF]

open access: yes, 2016
Global optimization of transition paths in complex atomic scale systems is addressed in the context of misfit dislocation formation in a strained Ge film on Si(001). Such paths contain multiple intermediate minima connected by minimum energy paths on the
A. Stukowski   +63 more
core   +2 more sources

Application of Improved PRD Algorithm Based on Burgers Vector Extraction and Analysis in Dislocation Loop Simulation

open access: yesYuanzineng kexue jishu, 2023
After neutron irradiation, RAFM steel will produce two types of interstitial dislocation loops (1/2〈111〉 loop and 〈100〉 loop), resulting in radiation hardening and embrittlement after long service.
XU Xincheng;NIE Ningming;WANG Jin;HE Xinfu;ZENG Yan;ZHANG Jilin;WANG Jue;WAN Jian
doaj  

Characterization of dislocation loops in hydrogen ion-implanted Fe-Cr alloy annealed at different temperatures

open access: yes工程科学学报, 2019
Reduced-activation ferritic/martensitic (RAFM) steels, based on Fe-Cr alloys, have been considered to be one of the most promising candidate structural materials for future fusion reactors.
DU Yu-feng, CUI Li-juan, WAN Fa-rong
doaj   +1 more source

Microstructural Characterization of Reactor Pressure Vessel Steels

open access: yesMetals, 2023
Ion irradiation is a promising tool to emulate neutron-irradiation effects on reactor pressure vessel (RPV) steels, especially in the situation of limited availability of suitable neutron-irradiated material.
Libang Lai   +4 more
doaj   +1 more source

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