锆合金包壳表面抗氧化涂层研究进展

Research Progress of Oxidation Resistance Coating on Zirconium Alloy Cladding

锆的热中子吸收截面低,具有优异的耐腐蚀性和较高的熔点(1852℃),因而在核燃料包壳管中被广泛应用。在日本核电站意外爆炸发生后,耐事故燃料(ATF)受到广泛关注,一种在锆合金表面制备涂层的方法因具有很高的经济性而被广泛研究。文中介绍了锆合金包壳表面涂层的抗高温氧化性能的研究现状,分析了近年来使用的金属、陶瓷、MAX相涂层对锆合金表面抗氧化性能的影响,指出Cr基涂层更有应用前景。

Zirconium is widely used in nuclear fuel cladding tubes due to its low thermal neutron absorption cross-section,excellent corrosion resistance,and high melting point(1852℃).After the accidental explosion of the Japanese nuclear power plant,accident tolerant fuel(ATF)has attracted much attention.A method of preparing coating on zirconium alloy surface has been widely studied because of its high economic performance.This paper reviews the research status of anti-oxidation performance of zirconium alloy surface coatings,analyzes the effects of metal coatings,ceramic coatings and MAX coatings on the oxidation resistance of zirconium alloy surfaces,and points out that Cr-based coatings have more advantages.