Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation

Chen, Lijun; Zhou, Hongling; Luan, Baifeng; Yang, Hongyan; Zhang, Ruiqian; Sun, Chao; Yang, Xiaoling; Liu, Congqing

doi:10.1016/j.jnucmat.2024.155113

Journal of Nuclear Materials

2024

DOI: 10.1016/j.jnucmat.2024.155113

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Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation

Lijun Chen,

Hongling Zhou,

Baifeng Luan

et al.

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Early-stage diffusion and oxidation behavior of Cr-Nb coated Zr alloy accident tolerant fuel cladding materials at 1200°C–1500°C

Yang,

Shang,

Zhao

et al. 2024

Journal of Nuclear Materials

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Early-stage diffusion and oxidation behavior of Cr-Nb coated Zr alloy accident tolerant fuel cladding materials at 1200°C–1500°C

Yang,

Shang,

Zhao

et al. 2024

Journal of Nuclear Materials

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Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation

Cited by 1 publication

References 73 publications

Early-stage diffusion and oxidation behavior of Cr-Nb coated Zr alloy accident tolerant fuel cladding materials at 1200°C–1500°C

Early-stage diffusion and oxidation behavior of Cr-Nb coated Zr alloy accident tolerant fuel cladding materials at 1200°C–1500°C

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