Electrothermal properties and interdiffusion behavior of Cr/Mo coated Zr-1Nb alloy under high temperature for corrosion resistance of nuclear reactor

This study investigates the high-temperature (HT) oxidation resistance and interdiffusion behavior of Cr/Mo thin-layer coatings on Zr-1Nb alloy, aimed at enhancing corrosion resistance in nuclear reactor components. Magnetron sputtered coatings Mo (3 μm)/Cr (8 μm) demonstrated significant improvements in oxidation resistance at 1100 °C. However, coating delamination occurred after 60 min, necessitating further optimization. Non-destructive testing (NDT) methods, including four probe point (FPP) resistivity and thermal electromotive force (thermoEMF) analysis, provided real-time insights into coating stability, highlighting their potential for advanced diagnostic applications. The findings suggest Cr/Mo-coated Zr-1Nb alloys as a promising material for accident-tolerant nuclear fuel claddings.

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Publication Details

Journal
Discover Materials
Published
2025-11-28
DOI
https://doi.org/10.1007/s43939-025-00483-5
Citations
1
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
0.52
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article

Electrothermal properties and interdiffusion behavior of Cr/Mo coated Zr-1Nb alloy under high temperature for corrosion resistance of nuclear reactor

А. М. Лидер, Abdelrahman M. Salman
1 citations
Discover Materials
Nuclear Materials and Properties
0.52
article

Electrothermal properties and interdiffusion behavior of Cr/Mo coated Zr-1Nb alloy under high temperature for corrosion resistance of nuclear reactor

А. М. Лидер, Abdelrahman M. Salman
article en
1 citations

Abstract

This study investigates the high-temperature (HT) oxidation resistance and interdiffusion behavior of Cr/Mo thin-layer coatings on Zr-1Nb alloy, aimed at enhancing corrosion resistance in nuclear reactor components. Magnetron sputtered coatings Mo (3 μm)/Cr (8 μm) demonstrated significant improvements in oxidation resistance at 1100 °C. However, coating delamination occurred after 60 min, necessitating further optimization. Non-destructive testing (NDT) methods, including four probe point (FPP) resistivity and thermal electromotive force (thermoEMF) analysis, provided real-time insights into coating stability, highlighting their potential for advanced diagnostic applications. The findings suggest Cr/Mo-coated Zr-1Nb alloys as a promising material for accident-tolerant nuclear fuel claddings.

Discover MaterialsVol. 5(1)
National Research Tomsk State University (RU), Tomsk Polytechnic University (RU)
Openalex Percentile: Top 30%
Nuclear Materials and Properties
0.52
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