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锆合金是水冷动力堆核燃料元件的包壳材料和堆芯的其它结构材料。在反应堆运行时,堆功率的波动和水冷却介质的流动使燃料组件及其它构件发生循环变形,在极端情况下出现破损。本文概述了堆内锆合金包壳循环变形的特点,并综述了锆合金的循环变形行为、循环变形下的组织结构演化、疲劳裂纹的扩展以及影响疲劳寿命的因素。在此基础上,针对高性能燃料元件的发展趋势,指出了有待进一步研究解决的问题。
Zircaloy is a cladding material for a nuclear fuel element of a water-cooled power reactor and other structural materials for the core. During reactor operation, fluctuations in stack power and the flow of water-cooling media cyclically deform fuel assemblies and other components and, in extreme cases, break down. In this paper, the characteristics of cycle deformation of zirconium alloy cladding in reactor are summarized. The cyclic deformation behavior of zirconium alloy, the evolution of microstructure under cyclic deformation, the expansion of fatigue crack and the factors affecting the fatigue life are summarized. On this basis, in view of the development trend of high-performance fuel elements, pointed out the problems to be further studied and solved.