锆合金均匀腐蚀模型研究进展

doi:10.11896/cldb.24120206

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Abstract Zirconium (Zr) alloys are widely used as key structural materials for pressurized water reactor fuel cladding due to their low thermal neutron absorption cross section, excellent corrosion resistance and mechanical properties. The uniform corrosion behavior of Zr alloys is one of the most critical factors limiting the service life of nuclear power fuel cladding. Therefore, establishing uniform corrosion models for Zr alloys is crucial for analyzing the corrosion behavior and predicting the service life of cladding materials. The existing uniform corrosion models for Zr alloys can be mainly divided into empirical models based on experimental data fitting and mechanism models based on corrosion micro mechanisms. This paper summarizes the research progress of current empirical and mechanistic models for uniform corrosion of Zr alloys, analyzes the advantages and disadvantages of the models, and proposes improvement directions for model development, beneficial for the construction and optimization of independent long-term uniform corrosion models for advanced Zr alloys.

Key words： zirconium alloy cladding material corrosion model oxidation kinetics

Published: 25 January 2026 Online: 2026-01-27

CLC number:	TL34
	TG146

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	Articles by authors
	PENG Danmin
	SUN Zhipeng
	HU Shuwei
	ZHOU Mingyang
	GAO Yang
	QIU Xi
	ZHANG Kun
	LI Yuanming

Cite this article:

PENG Danmin,SUN Zhipeng,HU Shuwei, et al. The Research Progress of Zirconium Alloy Uniform Corrosion Mechanism Models[J]. Materials Reports, 2026, 40(2): 24120206-7.

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https://www.mater-rep.com/EN/10.11896/cldb.24120206 OR https://www.mater-rep.com/EN/Y2026/V40/I2/24120206

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