The effect of stress state and He concentration on the dislocation loop evolution in Ni superalloy irradiated by Ni+ & He+ dual-beam ions: In-situ TEM observation and …

Z Zhu, R Qiu, L Chang, G Ma, H Deng… - Journal of Materials …, 2025 - Elsevier
In-situ TEM observation was conducted during Ni+ &He+ dual-beam irradiation to monitor
the evolution of dislocation loops accompanied by He bubbles in the Ni-based alloy …

STEM characterization of dislocation loops in irradiated FCC alloys

P Xiu, H Bei, Y Zhang, L Wang, KG Field - Journal of Nuclear Materials, 2021 - Elsevier
In this study, we demonstrate the methodology systematically developed for dislocation loop
(perfect and faulted loops) imaging and analysis in irradiated face-centered-cubic (FCC) …

Impact of micro-alloying in ion-irradiated nickel: From the inhibition of point-defect cluster diffusion by thermal segregation to the change of dislocation loop nature

K Ma, B Décamps, L Huang, RE Schäublin, JF Löffler… - Acta Materialia, 2023 - Elsevier
Micro-alloying strongly affects the incubation period of void swelling in irradiated face-
centered cubic materials. However, the underlying mechanism, which relates to the …

Free surface impact on radiation damage in pure nickel by in-situ self-ion irradiation: can it be avoided?

K Ma, B Décamps, A Fraczkiewicz, T Jourdan, F Prima… - Acta Materialia, 2021 - Elsevier
A major issue of in-situ radiation damage studies is related to the influence of free surfaces.
Free surfaces in thin foils are indeed strong sinks for radiation-induced defects …

Comparison of ion irradiation effects in PM-HIP and forged alloy 625

C Clement, Y Zhao, P Warren, X Liu, S Xue… - Journal of Nuclear …, 2022 - Elsevier
The nuclear industry has growing interest in replacing forgings with structural components
fabricated by powder metallurgy with hot isostatic pressing (PM-HIP), owing to their chemical …

Nested loops explain low irradiation-induced swelling rate

L Cui, Y Du, H Yang, RE Schäublin, Y Zongda, S Kano… - Acta Materialia, 2024 - Elsevier
In the quest of radiation and oxidation-resistant materials for the fuel claddings of nuclear
power stations, chromium (Cr) emerges as a good candidate. It shows a significantly lower …

Additive manufacturing of a Ni-20 wt% Cr binary alloy by laser powder bed fusion: Impact of the microstructure on the mechanical properties

E Hug, M Lelièvre, C Folton, A Ribet… - Materials Science and …, 2022 - Elsevier
In the present work, microstructure and mechanical properties of a binary Ni-20 wt% Cr alloy
manufactured by laser powder bed fusion process were investigated. It was shown that this …

In situ transmission electron microscopy studies of 30 keV H2+ and He+ dual-beam irradiated Pd: defect generation and microstructural evolution under varied …

XY Liu, YP Li, G Ran, Q Han, PH Chen - Materials Today Energy, 2021 - Elsevier
To fully understand the tritium aging behavior of palladium (Pd), an important material
applied in hydrogen isotope storage and tritium engineering, an in situ irradiation of 30 keV …

Solute-point defect interactions, coupled diffusion, and radiation-induced segregation in fcc nickel

E Toijer, L Messina, C Domain, J Vidal… - Physical Review …, 2021 - APS
Radiation-induced segregation (RIS) of solutes in materials exposed to irradiation is a well-
known problem. It affects the lifetime of nuclear reactor core components by favoring …

A Brief Review on He Ion Irradiation Research of Steel and Iron-Based Alloys in Nuclear Power Plants

S Qiu, H Liu, M Jiang, S Min, Y Gu, Q Wang… - Acta Metallurgica Sinica …, 2023 - Springer
Nuclear power plays a key role as renewable energy in alleviating the worldwide energy
shortage. The material degradation caused by high-temperature and high-flux neutron …