A tungsten deep neural-network potential for simulating mechanical property degradation under fusion service environment

X Wang, Y Wang, L Zhang, F Dai, H Wang - Nuclear Fusion, 2022 - iopscience.iop.org
Tungsten is a promising candidate material in fusion energy facilities. Molecular dynamics
(MD) simulations reveal the atomistic scale mechanisms, so they are crucial for the …

Microstructural analysis of W irradiated at different temperatures

M Klimenkov, M Dürrschnabel, U Jäntsch, P Lied… - Journal of Nuclear …, 2022 - Elsevier
Pure W was neutron irradiated at 600° C, 900° C, 1000° C, 1100° C, and 1200° C with a
dose of∼ 1 dpa, and its microstructure was subsequently analyzed using transmission …

The role of Cr concentration and temperature on cavity swelling with co-injected helium in dual-ion irradiated Fe and Fe-Cr alloys

YR Lin, A Bhattacharya, D Chen, Y Zhao, JJ Kai… - Materials & Design, 2022 - Elsevier
The level of chromium plays an essential role in irradiation tolerance of Fe-Cr ferritic alloys.
However, conflicting results have been reported regarding the dependence of cavity …

In-situ TEM investigation of dislocation loop reaction and irradiation hardening in H2+-He+ dual-beam irradiated Mo

Y Li, G Ran, X Liu, Q Han, X Huang, Y Ding - Journal of Materials Science & …, 2022 - Elsevier
Through in-situ TEM observation during 30 keV H 2+-He+ dual-beam irradiation at 723 K,
the reaction and transformation of dislocation loops in pure Mo were investigated, especially …

In-situ TEM investigation of dislocation loop evolution in Al-forming austenitic stainless steels during Fe+ irradiation: Effects of irradiation dose and pre-existing …

Z Ma, G Ran, X Qiu, Y Li, Y Ding, R Zhang… - Journal of Nuclear …, 2022 - Elsevier
Alumina-forming austenitic (AFA) stainless steel with excellent properties has been
regarded as a promising candidate of fuel claddings in Supercritical carbon dioxide (S-CO …

In-situ TEM study of the effect of pre-existing dislocation on loop evolution in 508-III steel during Fe+ irradiation

Y Luo, Y Dong, X Wang, H Peng, D Yan, T Hu… - Journal of Nuclear …, 2022 - Elsevier
This study explores the evolution processes of initiation, migration, growth, annihilation, and
aggregation for dislocation loops and dislocation complex formation in regions with and …

TEM investigation of neutron irradiated and post irradiation annealed tungsten materials

W Van Renterghem, G Bonny, D Terentyev - Fusion Engineering and …, 2022 - Elsevier
In this paper, we present a transmission electron microscopy study of three tungsten grades
subjected to neutron irradiation and post-irradiation annealing. The irradiation was …

Effect of solute elements (Ni, Mn) in Fe-based alloys on dislocation loop evolution under Fe2+ ion irradiation

PP Tom, K Murakami, VN Luu, BVC Nguyen… - Journal of Nuclear …, 2022 - Elsevier
The dislocation loop is known as one of the irradiation defects that contributes to hardening
and accompanying embrittlement in reactor pressure vessel steels. In this study, the effect of …

Relative population of 1/2< 111> and< 100> interstitial loops in alpha-Fe under irradiation: Effects of C15 cluster stability and loop one-dimensional movement

J Gao, E Gaganidze, J Aktaa - Acta Materialia, 2022 - Elsevier
Abstract The relative stability of 1/2< 111> and< 100> dislocation loops, originating from
anisotropic elasticity of alpha-Fe, was extensively exploited to explain experimentally …

Machine-learning interatomic potential for radiation damage effects in bcc-iron

Y Wang, J Liu, J Li, J Mei, Z Li, W Lai, F Xue - Computational Materials …, 2022 - Elsevier
We introduce a machine-learning interatomic potential for bcc iron based on the moment
tensor potential framework and a hybridization scheme of distinct sub-potentials. With an …