The Research Of Nuclear Pressure Vessel Material Fatigue Life Evaluation And Prediction Model

Pressurized water reactor(PWR) is served with a special primary coolant circuit water chemistry environment of high temperature and high pressure water, reactor pressure vessel serving as a pressure boundary supports some stress, so the service process may cause environmental damage issues which has a potential threat to the safe operation of the plant. According to the survey of the experience and the nuclear power plant operation, environment fatigue(CF)is one of the main potential forms of PWR pressure boundary material environment assisted crack.The paper studied the fatigue life of the domestic RPV material SA508-III in high temperature water environment, and the nuclear pressure vessel fatigue assessment method.1. Introduce the environment fatigue assessment process of nuclear power specified components, and environment fatigue analysis and calculation methods by ASME.2. By conducting domestic RPV steel SA508-III fatigue test in the air and high temperature water, the effect of stain rate and temperature on the fatigue life is studied, the material's S-N curve,and environment correction factor is calculated.3. Build the 3D model and finite element model for nuclear power pressure vessel, calculated the temperature field and stress field. Respectively calculated the environment correction factor(Fen)and fatigue damage factor(CUFen)by three methods of transient connection, calculated the effect of different input methods of stain rate and temperature on environment correction factor and fatigue damage factor.Finally, summarized the full paper, the current problems and future developments in this field are presented on the basis of a conclusion of this paper.