事故容错锆包壳表面Cr涂层的研究进展

Research Progress of Cr Coating on Fault Tolerant Zircon Crust

锆合金因具有热中子吸收截面低等特有的性质,被广泛应用于核反应堆中,在核反应堆中起到预防核泄漏的作用。核燃料包壳管中的锆在核反应堆内高温、高压的水环境下,极易与水蒸气发生氧化反应生成大量氢气,从而引起“氢爆”导致核事故。为此,研究能一定程度上包容事故和具有固有安全性的耐事故燃料(ATF),对锆合金表面涂层制备尤为重要,其中Cr涂层在所考虑的各种涂层材料中具有明显优势,发展和研究潜力最大,成为重点的研究方向之一。综合分析了近年来国内外锆包壳表面Cr涂层的研究现状。介绍了Cr涂层的制备技术及工艺特点,并对不同技术制备的涂层的性能分析进行整合。总结归纳了Cr涂层的高温氧化性能,对今后涂层的研究方向提出见解。为进一步提升核电站安全性和可靠性的重要举措提供参考。

Zirconium alloy is widely used in nuclear reactors because of its low thermal neutron absorption cross section,which plays a role in preventing nuclear leakage.Under the high temperature and high pressure water environment in the nuclear reactor,the zirconium in the nuclear fuel cladding tube is easy to oxidize with water vapor to generate a large amount of hydrogen,which leads to"hydrogen explosion"and nuclear accident.Therefore,the study of accident-resistant fuel(ATF)that can contain accidents to a certain extent and has inherent safety is particularly important for the preparation of zirconium alloy surface coating.Among all coating materials,Cr coating has obvious advantages and has the greatest development and research potential,and has become one of the key research directions.The research status of Cr coating on zircon crust was comprehensively analyzed.The preparation technology and process characteristics of Cr coatings were introduced,and the performance analysis of coatings prepared by different technologies was integrated.The high temperature oxidation properties of Cr coatings were summarized,and the future research direction of coatings was put forward.It provides reference for important measures to further improve the safety and reliability of nuclear power plants.