Microstructure and mechanical evolution of FeCrAlMo-xZr fuel cladding alloys during hot corrosion

The microstructural and mechanical evolution of the Fe-13Cr-6Al-2Mo- x Zr ( x = 0.15, 0.5, 1.0 wt%) alloys for fuel cladding throughout various hot corrosion processes, such as thermal aging at 475 °C in air and high temperature oxidation at 1200 °C under an atmosphere of Ar + water vapour, were investigated. The findings indicate that as the Zr content increases, the grain size of the alloys becomes progressively smaller. During thermal aging, the secondary Laves phase precipitated within the grains and Mo segregation occurred on the grain boundaries, ultimately forming the μ phase. The plasticity decreased by degrees with aging time due to the formation and growth of precipitates, while the tensile strength increased only during the early aging period and then remained almost unchanged. The steam oxidation rate was promoted with the Zr content because of the smaller grain size and the deeper internal oxidation resulting from the faster diffusion of oxygen in ZrO 2 than that in Al 2 O 3 .

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Publication Details

Journal
Nuclear Engineering and Technology
Published
2025-04-09
DOI
https://doi.org/10.1016/j.net.2025.103637
Citations
1
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
0.52
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article

Microstructure and mechanical evolution of FeCrAlMo-xZr fuel cladding alloys during hot corrosion

Chundong Wang, Jie Pan, Huawei Zhang, Cong Li et al.
1 citations
Nuclear Engineering and Technology
Nuclear Materials and Properties
0.52
article

Microstructure and mechanical evolution of FeCrAlMo-xZr fuel cladding alloys during hot corrosion

Chundong Wang, Jie Pan, Huawei Zhang, Cong Li, Jun Li, Jiwei Lin, Ping Cao, Xueshan Xiao, Xijie Wu, Cheng Su, Meiyi Yao
article en
1 citations

Abstract

The microstructural and mechanical evolution of the Fe-13Cr-6Al-2Mo- x Zr ( x = 0.15, 0.5, 1.0 wt%) alloys for fuel cladding throughout various hot corrosion processes, such as thermal aging at 475 °C in air and high temperature oxidation at 1200 °C under an atmosphere of Ar + water vapour, were investigated. The findings indicate that as the Zr content increases, the grain size of the alloys becomes progressively smaller. During thermal aging, the secondary Laves phase precipitated within the grains and Mo segregation occurred on the grain boundaries, ultimately forming the μ phase. The plasticity decreased by degrees with aging time due to the formation and growth of precipitates, while the tensile strength increased only during the early aging period and then remained almost unchanged. The steam oxidation rate was promoted with the Zr content because of the smaller grain size and the deeper internal oxidation resulting from the faster diffusion of oxygen in ZrO 2 than that in Al 2 O 3 .

Nuclear Engineering and TechnologyVol. 57(9)
Shanghai University (CN), Shanghai Research Institute of Materials (CN)
Affordable and clean energy
Openalex Percentile: Top 40%
Nuclear Materials and Properties
0.52
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Microstructure and mechanical evolution of FeCrAlMo-xZr fuel cladding alloys during hot corrosion — Chundong Wang, Jie Pan, et al. · Nuclear Engineering and Technology (2025) | TGRS Research Map | TGRS