反应堆压力容器(RPV)和一回路主管道是影响核电站经济性和安全性的关键部件。RPV及主管道的设计寿命主要依据材料在一回路水环境的疲劳模型制定。我国正在大力发展具有自主产权的第3代核电,但尚未建立国产材料的疲劳模型,对国产三代堆关键部件的设计寿命评估造成困难。因此,开展相关研究的需求十分迫切。本文开展了一回路水环境的疲劳实验研究,建立了国产SA508-Ⅲ锻件以及一回路主管道 Reactor pressure vessels (RPVs) and primary loop main piping are key components that affect the economics and safety of nuclear power plants. The design life of the RPV and the main pipeline is mainly based on the fatigue model of the material in the water environment of the primary circuit. Our country is vigorously developing the third generation nuclear power with independent property rights, but the fatigue model of domestic materials has not yet been established, which makes it difficult to evaluate the design life of the key components of the third generation of the Chinese generation. Therefore, the need to carry out relevant research is urgent. This paper carried out a loop of water environment fatigue experimental study, the establishment of the domestic SA508-Ⅲ forgings and a loop of the main pipeline