Analytic model for the Orowan dislocation-precipitate bypass mechanism

BA Szajewski, JC Crone, J Knap - Materialia, 2020 - Elsevier
The interaction between glissile dislocations and precipitates within a continuum is
responsible for marked increases in material strength. Due to their desirable engineering …

Theoretical models for irradiation hardening and embrittlement in nuclear structural materials: a review and perspective

X Xiao, D Terentyev, H Chu, H Duan - Acta Mechanica Sinica, 2020 - Springer
The study of irradiation hardening and embrittlement is critically important for the
development of next-generation structural materials tolerant to neutron irradiation, and could …

Trends in vacancy distribution and hardness of high temperature neutron irradiated single crystal tungsten

G Bonny, MJ Konstantinovic, A Bakaeva, C Yin… - Acta Materialia, 2020 - Elsevier
The aim of the present study is to extend the knowledge about the formation and thermal
stability of vacancy-type defects in tungsten under neutron irradiation, thereby mimicking the …

Atomistic simulations of dynamics of an edge dislocation and its interaction with a void in copper: a comparative study

WR Jian, M Zhang, S Xu… - Modelling and Simulation …, 2020 - iopscience.iop.org
Atomistic simulation methods are appropriate tools for investigating the dynamics of
dislocations and their interactions with obstacles in metallic materials. In particular …

[HTML][HTML] Defect accumulation and evolution during prolonged irradiation of Fe and FeCr alloys

F Granberg, J Byggmästar, K Nordlund - Journal of Nuclear Materials, 2020 - Elsevier
The understanding of materials' behaviour during continuous irradiation is of great interest
for utilizing materials in environments where harsh radiation is present, like nuclear power …

[HTML][HTML] Dislocation-oxide interaction in Y2O3 embedded Fe: A molecular dynamics simulation study

MM Azeem, Q Wang, Z Li, Y Zhang - Nuclear Engineering and Technology, 2020 - Elsevier
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 …

An unified model for dislocations interacting with complex-shape voids in irradiated metals

Y Chen, Y Liu, Q Fang, J Li, Y Liu, PK Liaw - International Journal of …, 2020 - Elsevier
The irradiation damage-induced voids can hinder dislocation glide, and thereby change the
mechanical properties in the nuclear materials. However, the detailed process of the …

The effect on the mechanical response of Cr and Ni segregation on dislocation lines in bcc Fe

MI Pascuet, G Bonny, G Monnet, L Malerba - Journal of Nuclear Materials, 2020 - Elsevier
The understanding of irradiation-induced strengthening in ferritic-martensitic high-Cr steels
remains an essential issue in the assessment of materials for fusion and next generation …