In-situ electrochemistry and mechanism investigation of the enhanced corrosion resistance of Zr-Sn-Nb alloy enabled by self-ion implantation

High-temperature aqueous corrosion significantly limits the lifespan of zirconium alloys in high-burnup pressurized water reactors. This study evaluates the effect of self-ion implantation on the corrosion behavior of the N36 alloy. Corrosion tests were performed on N36 alloys implanted with various Zr 2+ doses, followed by in-situ electrochemical tests in 360 o C lithiated/borated water. Results showed that Zr 2+ implantation induced surface hardening and promoted elements segregation and dilution, resulting in a notable reduction in corrosion rates, particularly at higher doses. The influence of Zr 2+ implantation on corrosion was validated by potentiodynamic polarization and electrochemical impedance spectroscopy, and the mechanisms were discussed. The implantation-induced effects synergistically stabilize the protective t-ZrO 2 phase. This promotes the formation of a denser, more protective oxide film, characterized by mitigated porosity in the outer layer and a refined inner columnar structure. Consequently, the densified oxide film acts as a superior barrier, leading to an improvement in corrosion performance.

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Journal
Journal of Materials Research and Technology
Published
2026-03-15
DOI
https://doi.org/10.1016/j.jmrt.2026.03.144
Primary Topic
Nuclear Materials and Properties
Type
article
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article

In-situ electrochemistry and mechanism investigation of the enhanced corrosion resistance of Zr-Sn-Nb alloy enabled by self-ion implantation

Siyao Qiu, Zhuqing Cheng, Jiali Liao, Tianxu Chen et al.
Journal of Materials Research and Technology
Nuclear Materials and Properties
article

In-situ electrochemistry and mechanism investigation of the enhanced corrosion resistance of Zr-Sn-Nb alloy enabled by self-ion implantation

Siyao Qiu, Zhuqing Cheng, Jiali Liao, Tianxu Chen, Zhongbo Yang, Shasha Lv, Yiran Cui
article en

Abstract

High-temperature aqueous corrosion significantly limits the lifespan of zirconium alloys in high-burnup pressurized water reactors. This study evaluates the effect of self-ion implantation on the corrosion behavior of the N36 alloy. Corrosion tests were performed on N36 alloys implanted with various Zr 2+ doses, followed by in-situ electrochemical tests in 360 o C lithiated/borated water. Results showed that Zr 2+ implantation induced surface hardening and promoted elements segregation and dilution, resulting in a notable reduction in corrosion rates, particularly at higher doses. The influence of Zr 2+ implantation on corrosion was validated by potentiodynamic polarization and electrochemical impedance spectroscopy, and the mechanisms were discussed. The implantation-induced effects synergistically stabilize the protective t-ZrO 2 phase. This promotes the formation of a denser, more protective oxide film, characterized by mitigated porosity in the outer layer and a refined inner columnar structure. Consequently, the densified oxide film acts as a superior barrier, leading to an improvement in corrosion performance.

Journal of Materials Research and TechnologyVol. 42
Beijing Normal University (CN), Key Laboratory of Nuclear Radiation and Nuclear Energy Technology (CN)
Clean water and sanitation
Openalex Percentile: Top 23%
Nuclear Materials and Properties
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In-situ electrochemistry and mechanism investigation of the enhanced corrosion resistance of Zr-Sn-Nb alloy enabled by self-ion implantation — Siyao Qiu, Zhuqing Cheng, et al. · Journal of Materials Research and Technology (2026) | TGRS Research Map | TGRS