【作者】 杭华江；

【导师】 李润方；

【作者基本信息】 重庆大学 ， 机械设计及理论， 2003， 硕士

【摘要】 本论文来源于国防科学技术工业委员会关于先进压水堆核电站先进反应堆设计技术研究项目（批文号：科工委[1999]149号）的子课题“反应堆压力容器瞬态密封程序研制”。本课题研究的目的是为核电站国产化及自主设计提供技术准备，提高设计质量和设计水平，确保先进压水堆核容器密封系统设计的可靠性，确保核安全，使核容器密封设计软件达到世界先进水平。 本文开发了反应堆压力容器瞬态密封有限元分析程序FEARPV的前处理程序，实现了参数化的有限元分析模型的自动生成，建立较接近反应堆压力容器密封结构实际情况的计算模型。 应用反应堆压力容器瞬态密封有限元分析程序对反应堆压力容器模拟体密封结构进行了螺栓预紧、升温升压、恒温恒压、降温降压等全过程分析。所得计算结果与中国核动力运行研究所（武汉）和中国核动力院设计研究所在压力容器模拟体上所测的大量应力、应变、温度、螺栓力、分离量等数据进行了对比，在两种载荷工况下，无论是冷态还是热态，无论是定性规律还是定量数据，分析结果和实验结果都吻合良好。 应用反应堆压力容器瞬态密封有限元分析程序对电站核压力容器密封结构进行了螺栓预紧、升温升压、恒温恒压、降温降压等全过程的三维瞬态密封分析。由本文分析计算可知，虽然电站核压力容器的结构及计算工况较压力容器模拟体复杂得多，然而反应堆压力容器瞬态密封有限元分析程序对塑性迭代和接触迭代仍具有很好的收敛性，数值稳定性好，得到的结果具有良好的规律性，在升温、升压、恒温、恒压、降温和降压等过程中其规律和压力容器模拟体基本相似。计算结果表明，由于密封区斜面的存在，使密封面的接触区增大，接触压力分布更趋合理，并有助于减小内外槽的分离量。更多还原

【Abstract】 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 and<WP=6>contact 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.更多还原