The evolution of dislocation loop and its interaction with pre-existing dislocation in He+-irradiated molybdenum: in-situ TEM observation and molecular dynamics …

Y Li, G Ran, Y Guo, Z Sun, X Liu, Y Li, X Qiu, Y Xin - Acta Materialia, 2020 - Elsevier
In-situ TEM observation and molecular dynamics simulation were used to investigate the
evolution of irradiation-induced dislocation loops and their interactions with the pre-existing …

He ion irradiation response of a gradient T91 steel

Z Shang, J Ding, C Fan, D Chen, J Li, Y Zhang, Y Wang… - Acta Materialia, 2020 - Elsevier
Metallic materials with a gradient microstructure usually exhibit excellent mechanical
properties. However, the radiation response of gradient structural materials is less well …

[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 …

Off-lattice kinetic monte carlo methods

M Trochet, N Mousseau, LK Béland… - Handbook of materials …, 2020 - Springer
Exact modeling of the dynamics of chemical and material systems over experimentally
relevant time scales still eludes us even with modern computational resources. Fortunately …

Nitrogen effects on radiation response in 12Cr ferritic/martensitic alloys

E Aydogan, JG Gigax, SS Parker, BP Eftink, M Chancey… - Scripta Materialia, 2020 - Elsevier
Ferritic/martensitic steels are one of the best candidates for structural materials for high dose
applications in next generation nuclear reactors. The composition of structural materials …

Effect of Si–Ni–P on the emergence of dislocations loops in Fe–9Cr matrix under neutron irradiation: TEM study and OKMC modelling

A Dubinko, N Castin, D Terentyev, G Bonny… - Journal of Nuclear …, 2020 - Elsevier
The expected degradation of mechanical properties of structural materials under irradiation
(ie “in operation”) in nuclear components represents a significant challenge for the design to …

In-situ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing

Y Du, K Yoshida, Y Shimada, T Toyama, K Inoue… - Materialia, 2020 - Elsevier
To better understand the thermal stability of dislocation loops formed by long-term neutron
irradiation in reactor pressure vessel (RPV) steels, in-situ scanning transmission electron …

Kinetic Monte Carlo simulations of irradiation effects

C Becquart, N Mousseau, C Domain - 2020 - lilloa.univ-lille.fr
Monte Carlo (MC) techniques are among the most used techniques for modeling materials
at the atomic scale, with those of molecular dynamics. The name MC comes from the fact …

Dislocation loop evolution in F/M steel T91 under in-situ ion irradiation: Influence of the presence of initial dislocations

C Zheng, D Kaoumi - Journal of Nuclear Materials, 2020 - Elsevier
Abstract Ferritic/Martensitic (F/M) steel T91 was irradiated in-situ to 4 and 10 dpa at 470° C
using 1 MeV Kr 2+. The microstructure evolution under irradiation was followed and …

Influence of helium-decoration on the interaction between 1/2< 111> dislocation loop and edge dislocation in BCC iron

B Zhu, M Huang, Z Li - Journal of Nuclear Materials, 2020 - Elsevier
For ferritic steels served as structural materials for future nuclear reactors, a large number of
helium atoms are expected to be introduced through transmutation reaction. Current …