Tian Liang

Ms. Tian Liang


Research Focus & Metrics

Academic Career Length

2Years (2025-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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16 April 2025 in Materials
Verified
Journal Article
Open access
PDF file
TLTian Liang
Tian Liang
JLJian Liu
Jian Liu
CZChi Zhan
Chi Zhan
SPShaoyuan Peng
Shaoyuan Peng
JPJibin Pu
Jibin Pu
Zr-4 alloy tubes, as the primary cladding material in nuclear reactor cores, face the critical challenge of oxidative attack in 1200 °C steam environments. To address this issue, high-temperature oxidation-resistant coatings fabricated via extreme high-speed laser cladding (EHLA) present a promising mitigation strategy. In this study, Y2O3-modified (0.0–5.0 wt.%) Cr/FeCrAl composite coatings were designed and fabricated on Zr-4 substrates using the EHLA process, followed by systematic investigation of Y doping effects on coating microstructures and steam oxidation resistance (1200 °C, H2O atmosphere). Experimental results demonstrate that Y2O3 doping remarkably enhanced the oxidation resistance, with optimal performance achieved at 2.0 wt.% Y2O3 (31% oxidation mass gain compared to the substrate after 120-min exposure). Microstructural analysis reveals that the dense grain boundary network facilitates rapid surface diffusion of Al, promoting continuous Al2O3 protective film formation. Additionally, Y segregation at grain boundaries suppressed outward diffusion of Cr3+ cations, effectively inhibiting void formation at the oxide-coating interface and improving interfacial stability. The developed rare-earth-oxide-doped composite coating via extreme high-speed laser cladding process shows promising applications in surface-strengthening engineering for nuclear reactor Zr-4 alloy cladding tubes, providing both theoretical insights and technical references for the design of high-temperature oxidation-resistant coatings in nuclear industry.