Evolution of Cr/Cr2O3 interface in Cr-coated zirconium alloy in high temperature steam

Yao Wang; Bo Chen; Xian Zong Wang; Mingju Chen; Shilei Li; Guanghai Bai; Jinshan Li; Weijia Gong

doi:10.1016/j.corsci.2023.111099

Evolution of Cr/Cr₂O₃ interface in Cr-coated zirconium alloy in high temperature steam

Yao Wang, Bo Chen, Xian Zong Wang, Mingju Chen, Shilei Li, Guanghai Bai, Jinshan Li, Weijia Gong

School of Materials Sience and Engineering

Research output: Contribution to journal › Article › peer-review

27 Scopus citations

Abstract

<100> textured Cr-coating was deposited on Zr-based nuclear fuel cladding and went through steam oxidation at 1200 °C. The formed Cr₂O₃ layer exhibited thickening-thinning transition characteristic accompanying undulation of the Cr/Cr₂O₃ interface with oxidation progress. Electron microscopy characterization revealed that the convex tips of Cr/Cr₂O₃ interface invariably linked to grain boundaries of residual Cr-coating, which channeled the outward diffusion of Zr atoms consequently reducing Cr₂O₃-grains into Cr-grains. The reduction reaction at the Cr/Cr₂O₃ interface accounts for the interface undulation and consumption of protective oxides. This study is expected to shed light on failure mechanism of protective oxides on ATF Cr-coatings.

Original language	English
Article number	111099
Journal	Corrosion Science
Volume	217
DOIs	https://doi.org/10.1016/j.corsci.2023.111099
State	Published - Jun 2023

Keywords

ATF cladding
Cr-coating
EBSD
High temperature oxidation
Interface
Reduction

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title = "Evolution of Cr/Cr2O3 interface in Cr-coated zirconium alloy in high temperature steam",

abstract = "<100> textured Cr-coating was deposited on Zr-based nuclear fuel cladding and went through steam oxidation at 1200 °C. The formed Cr2O3 layer exhibited thickening-thinning transition characteristic accompanying undulation of the Cr/Cr2O3 interface with oxidation progress. Electron microscopy characterization revealed that the convex tips of Cr/Cr2O3 interface invariably linked to grain boundaries of residual Cr-coating, which channeled the outward diffusion of Zr atoms consequently reducing Cr2O3-grains into Cr-grains. The reduction reaction at the Cr/Cr2O3 interface accounts for the interface undulation and consumption of protective oxides. This study is expected to shed light on failure mechanism of protective oxides on ATF Cr-coatings.",

keywords = "ATF cladding, Cr-coating, EBSD, High temperature oxidation, Interface, Reduction",

author = "Yao Wang and Bo Chen and Wang, {Xian Zong} and Mingju Chen and Shilei Li and Guanghai Bai and Jinshan Li and Weijia Gong",

note = "Publisher Copyright: {\textcopyright} 2023 Elsevier Ltd",

year = "2023",

month = jun,

doi = "10.1016/j.corsci.2023.111099",

language = "英语",

volume = "217",

journal = "Corrosion Science",

issn = "0010-938X",

publisher = "Elsevier Ltd",

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TY - JOUR

T1 - Evolution of Cr/Cr2O3 interface in Cr-coated zirconium alloy in high temperature steam

AU - Wang, Yao

AU - Chen, Bo

AU - Wang, Xian Zong

AU - Chen, Mingju

AU - Li, Shilei

AU - Bai, Guanghai

AU - Li, Jinshan

AU - Gong, Weijia

PY - 2023/6

Y1 - 2023/6

N2 - <100> textured Cr-coating was deposited on Zr-based nuclear fuel cladding and went through steam oxidation at 1200 °C. The formed Cr2O3 layer exhibited thickening-thinning transition characteristic accompanying undulation of the Cr/Cr2O3 interface with oxidation progress. Electron microscopy characterization revealed that the convex tips of Cr/Cr2O3 interface invariably linked to grain boundaries of residual Cr-coating, which channeled the outward diffusion of Zr atoms consequently reducing Cr2O3-grains into Cr-grains. The reduction reaction at the Cr/Cr2O3 interface accounts for the interface undulation and consumption of protective oxides. This study is expected to shed light on failure mechanism of protective oxides on ATF Cr-coatings.

AB - <100> textured Cr-coating was deposited on Zr-based nuclear fuel cladding and went through steam oxidation at 1200 °C. The formed Cr2O3 layer exhibited thickening-thinning transition characteristic accompanying undulation of the Cr/Cr2O3 interface with oxidation progress. Electron microscopy characterization revealed that the convex tips of Cr/Cr2O3 interface invariably linked to grain boundaries of residual Cr-coating, which channeled the outward diffusion of Zr atoms consequently reducing Cr2O3-grains into Cr-grains. The reduction reaction at the Cr/Cr2O3 interface accounts for the interface undulation and consumption of protective oxides. This study is expected to shed light on failure mechanism of protective oxides on ATF Cr-coatings.

KW - ATF cladding

KW - Cr-coating

KW - EBSD

KW - High temperature oxidation

KW - Interface

KW - Reduction

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U2 - 10.1016/j.corsci.2023.111099

DO - 10.1016/j.corsci.2023.111099

M3 - 文章

AN - SCOPUS:85150240060

SN - 0010-938X

VL - 217

JO - Corrosion Science

JF - Corrosion Science

M1 - 111099

ER -

Evolution of Cr/Cr₂O₃ interface in Cr-coated zirconium alloy in high temperature steam

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Keywords

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