Microstructural evolution and mechanical response of ion-irradiated Fe-9Cr alloys: Insights from nanoindentation

• Smaller indenters measure higher shear stress than larger spherical ones. • RT irradiation increases loop density, strengthening and hardening the material. • Dense loops from RT irradiation raise critical stress, hindering dislocation motion. • At 300 °C, loops near dislocations enable channels, easing dislocation glide. Understanding the mechanical behavior of Fe-Cr alloys under irradiation is crucial for their application in nuclear environments. This study investigates the evolution of dislocation structures and their impact on the nanoindentation response of Fe-9Cr alloys in five distinct conditions: (1) non-irradiated pristine material, (2) non-irradiated material annealed at 300 °C, (3) material irradiated with 10 MeV Fe²⁺ ions to 5 dpa at room temperature, (4) material irradiated with 10 MeV Fe²⁺ ions to 1 dpa at 300 °C, and (5) material irradiated with 10 MeV Fe²⁺ ions to 5 dpa at 300 °C. Transmission electron microscopy (TEM) analysis revealed that irradiation at RT leads to a dense distribution of dislocation loops, which act as strong obstacles to dislocation glide, significantly increasing the critical stress required for plastic deformation. In contrast, irradiation at 300 °C results in a lower density of defects in the matrix, with dislocation loops observed near pre-existing dislocation lines. This defect configuration facilitates the formation of dislocation channels, reducing overall obstruction to dislocation motion and leading to a decrease in pop-in stress compared to RT-irradiated samples. However, despite the apparent increase in dislocation mobility, Cr-decorated dislocation loops in the 300 °C-irradiated sample act as pinning sites, impeding the contribution of pre-existing dislocations to plastic deformation and necessitating the nucleation of new dislocations. Recorded mechanical properties, together with microstructural evolution, provide critical insights into the mechanical response of Fe-Cr alloys, offering valuable implications for their performance in nuclear applications.

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Publication Details

Journal
Journal of Nuclear Materials
Published
2025-08-14
DOI
https://doi.org/10.1016/j.jnucmat.2025.156109
Citations
3
Primary Topic
Prenatal Screening and Diagnostics
Type
article
Field-Weighted Citation Impact
10.48
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article

Microstructural evolution and mechanical response of ion-irradiated Fe-9Cr alloys: Insights from nanoindentation

3 citations
Journal of Nuclear Materials
Prenatal Screening and Diagnostics
10.48
article

Microstructural evolution and mechanical response of ion-irradiated Fe-9Cr alloys: Insights from nanoindentation

article en
3 citations

Abstract

• Smaller indenters measure higher shear stress than larger spherical ones. • RT irradiation increases loop density, strengthening and hardening the material. • Dense loops from RT irradiation raise critical stress, hindering dislocation motion. • At 300 °C, loops near dislocations enable channels, easing dislocation glide. Understanding the mechanical behavior of Fe-Cr alloys under irradiation is crucial for their application in nuclear environments. This study investigates the evolution of dislocation structures and their impact on the nanoindentation response of Fe-9Cr alloys in five distinct conditions: (1) non-irradiated pristine material, (2) non-irradiated material annealed at 300 °C, (3) material irradiated with 10 MeV Fe²⁺ ions to 5 dpa at room temperature, (4) material irradiated with 10 MeV Fe²⁺ ions to 1 dpa at 300 °C, and (5) material irradiated with 10 MeV Fe²⁺ ions to 5 dpa at 300 °C. Transmission electron microscopy (TEM) analysis revealed that irradiation at RT leads to a dense distribution of dislocation loops, which act as strong obstacles to dislocation glide, significantly increasing the critical stress required for plastic deformation. In contrast, irradiation at 300 °C results in a lower density of defects in the matrix, with dislocation loops observed near pre-existing dislocation lines. This defect configuration facilitates the formation of dislocation channels, reducing overall obstruction to dislocation motion and leading to a decrease in pop-in stress compared to RT-irradiated samples. However, despite the apparent increase in dislocation mobility, Cr-decorated dislocation loops in the 300 °C-irradiated sample act as pinning sites, impeding the contribution of pre-existing dislocations to plastic deformation and necessitating the nucleation of new dislocations. Recorded mechanical properties, together with microstructural evolution, provide critical insights into the mechanical response of Fe-Cr alloys, offering valuable implications for their performance in nuclear applications.

Journal of Nuclear MaterialsVol. 616
Warsaw University of Technology (PL), National Centre for Nuclear Research (PL), VTT Technical Research Centre of Finland (FI)
Openalex Percentile: Top 2%
Prenatal Screening and Diagnostics
10.48
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