首页|锆合金表面高温抗氧化涂层的研究进展

锆合金表面高温抗氧化涂层的研究进展

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锆合金因其热中子吸收截面小、热膨胀系数低,以及与UO2良好的相容性而成为当前核反应堆中主要的构件材料.然而,在高温蒸汽氧化环境中,锆合金会快速氧化失效,并产生大量氢气,从而引发氢爆炸.为了提高核反应堆的安全性,对锆合金表面进行强化形成高温抗氧化防护涂层,是解决这一难题的有效途径.本文介绍了锆合金表面高温氧化行为,重点综述了高温抗氧化涂层(包括金属涂层、陶瓷涂层以及复合涂层)的氧化行为和失效机理,对比分析了不同锆合金表面涂层高温氧化性能.另外,还对锆合金表面高温抗氧化涂层的多元素成分设计、制备方法和梯度结构设计的发展方向进行了展望.
Research progress of high-temperature oxidation-resistant coatings on surface zirconium alloy
Zirconium alloys have become the primary structural materials in current nuclear reactors due to their low thermal neutron absorption cross-section,low thermal expansion coefficient and excellent compatibility with UO2.However,in high-temperature steam oxidation environments,zirconium alloys quickly oxidize and fail,generating large amounts of hydrogen and leading to hydrogen explosions.In order to enhance the safety of nuclear reactors,it is imperative to strengthen the surface of zirconium alloys to form high-temperature oxidation-resistant protective coatings,which represents an effective approach to addressing this challenge.This paper introduces the high-temperature oxidation behavior of zirconium alloy surfaces,focusing on the oxidation behavior and failure mechanisms of high-temperature oxidation-resistant coatings(including metal coatings ceramic coatings,and composite coatings),and comparatively analyzes the high-temperature oxidation performance of different coatings on surface of zirconium alloys.The development progress of multi-element composition design,preparation methods,and gradient structure design of high-temperature oxidation-resistant coatings on zirconium alloy surfaces were discussed.

zirconium alloysteam oxidationhigh-temperature oxidation-resistant coatingsthermal expansion coefficient

朱林丹、肖华强、任丽蓉、肖易、莫太骞、林波、田雨鑫

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贵州大学 机械工程学院,贵阳 550025

贵州民族大学 物理与机电工程学院,贵阳 550025

中国铁路成都局集团有限公司 贵阳机务段,贵阳 550005

中山大学 材料学院,广州 518107

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锆合金 蒸汽氧化 高温抗氧化涂层 热膨胀系数

国家自然科学基金资助项目贵州省基础研究计划资助项目

52065009黔科合基础-ZK[2024]重点031

2024

中国有色金属学报
中国有色金属学会

中国有色金属学报

CSTPCD北大核心
影响因子:1.108
ISSN:1004-0609
年,卷(期):2024.34(9)