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

38 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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10.1016/j.corsci.2023.111099

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@article{6df0bd960445420d9410f7559654a772,

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",

}

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

UR - https://www.scopus.com/pages/publications/85150240060

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

Abstract

Keywords

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