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Ｚｒ４合金是压水堆核电厂核燃料包壳使用的材料。目前人们对国产Ｚｒ４合金实际疲劳性能了解甚少。本文按照我国的相关国家标准测试了该材料的常温常规力学性能和应变疲劳性能。得到Ｚｒ４合金在常温条件下的力学性能参数和疲劳裂纹疲劳性能参数。试验结果表明，国产Ｚｒ４合金在常温环境下的循环载荷作用下材料无硬化或软化现象。本文应用美国ＡＳＭＥＳｅｃⅢ以疲劳分析为基础的设计方法对疲劳试验结果进行处理，获得了常温条件下参考设计疲劳曲线，可供采用国产Ｚｒ４合金的结构在设计时参考或使用。
Zr 4 alloy PWR nuclear power plant nuclear fuel cladding material used. At present, people have little understanding of the actual fatigue properties of domestic Zr 4 alloy. In this paper, according to the relevant national standards of our test the material at room temperature conventional mechanical properties and strain fatigue properties. Zr 4 alloy obtained at room temperature mechanical properties parameters and fatigue crack fatigue performance parameters. Test results show that the material made of Zr-4 alloy under normal cyclic loading does not harden or soften. In this paper, the design method based on fatigue analysis of American ASMESecⅢ is used to deal with the fatigue test results. The fatigue curve of the reference design under normal temperature conditions is obtained, which can be used for the design or reference of the structure of domestic Zr4 alloy.