Sealing Analysis Under Cooling And Heating Cycle For Reactor Pressure Vessel In Nuclear Power Station

The theme comes from the project The Program Development for Transient Sealing in Reactor Pressure Vessel. This project is the subproject of the research project commissioned by the Technical Industry Committee, Department of Defense, which is about the advanced reactor design in advanced pressurized water reactor nuclear power station. The aim of this research project is to supply the technical preparation for the nuclear power station domestalization and autonomous design, to improve the design quality and level, to ensure the reliability of the sealing system in the advanced pressurized water reactor vessel, to ensure the nuclear safety, and to raise the design software level of the nuclear vessel sealing system to the advanced world class. In this thesis, the pre-processing program of FEARPV (Finite Element Analysis for Sealing System in Reactor Pressure Vessel) is developed, parameterization finite element automatical modeling is achieved, and computational model which is close to actual sealing system structure in the reactor pressure vessel is built. The program FEARPV is applied to analysis the sealing structure of the pressure vessel model during the total process, including bolt pretensioning process, heating and compression process, thermostated heating and constant pressure process, and the cooling and decompressing process. Then the computational results are compared with the experimental data including stress, strain, temperature, bolt force and separation, which are obtained by the China Nuclear Power Operation Research Institute (Wuhan) and China Nuclear Power Academy Design Research Institute. Either under cooling or heating cycle, no matter the qualitative regularity or quantitative data, the computational results are in common with the experimental data. The program FEARPV is applied to 3-D Transient sealing analysis of nuclear pressure vessel during the total process, including bolt pretensioning process, heating and compression process, thermostated heating and constant pressure process, and the cooling and decompressing process. According to the analysis and computational results in this thesis, although the actual structure and work conditions of the pressure vessel in nuclear power station are much more complex than that of the pressure vessel model, the program FEARPV still can get quite good convergence on the plasticity andcontact iteration. And also the program FEARPV has good value stability, and good regularity. During the heating, compression, constant temperature, constant pressure, cooling and decompression process, the regularity is basically in common with that of the pressure vessel model. According to the computational results, due to the existence of sealing zone slope, the contact zone of sealing zone is increased, the distribution of contact stress become more reasonable, and the separation of inner and outer canal is decreased.