复杂非均质地基隔震核电厂房系统的抗震性能与适应性研究

The seismic capacity, foundation adaptability, reliabilities of isolated nuclear power plant (NPP) and internal equipment are always key technical issues for the isolated NPP during the working time. In this research project, theoretical analysis and fine finite element method are adapted to investigate the dynamical response and deformation behaviors of isolated NPP and isolators by parametric analysis approach under different intensity earthquakes. The seismic vulnerability and ultimate earthquake resistance are studied deeply, the seismic fortification criterion SL-1 and SL-2 are also proposed in this research projects. Accordingly, considering the SSI effects and parametric uncertainties, the response characteristics and foundation adaptability of isolated NPP under non-homogeneous site conditions are analyzed completely and revealed. Thus, the limit state equation of isolated NPP is developed by deformation criterion in order to calculate the failure probability. Finally, seismic reliability of isolated NPP are presented under strong ground motions in this project. The research results achieved in this research project will provide not only new theoretical analysis model but also calculated method used to study the seismic safety analysis of the isolated NPP. The research results can also provide theoretical and technical basis for the application and promotion of isolated NPP in China.

隔震核电厂房结构在服役期间的抗震能力、复杂场地的适应性、结构和内部设备的可靠度依然是隔震核电厂发展所面临的关键技术问题。本项目拟采用理论分析和精细有限元等研究手段，研究隔震核电厂房结构及其隔震系统在不同强度地震作用下的动力响应和变形特征，重点探讨隔震核电厂房的地震易损性和极限抗震能力，完善隔震核电厂的抗震设防水准SL-1和SL-2；考虑土-结构相互作用和参数不确定性，重点分析不同场地条件下隔震核电厂房的响应特征，揭示非均匀场地条件下隔震核电厂房的地基适应性规律；采取变形准则，建立隔震核电厂房的极限状态方程，得到不同强度地震作用下隔震核电厂房及内部设备的失效概率和抗震可靠度。项目成果不仅为强震作用下核电厂的抗震安全分析提供新的分析模型和计算方法，也为隔震核电厂在我国的应用和推广提供理论和技术依据。

日本311地震造成福岛核电厂严重核事故，引起全世界对核电安全的关注，强震作用下核电站安全服役已成为核电工程领域亟需解决的关键科学问题。隔震技术作为一种有效和可靠的手段，已广泛地应用于民用和工业建筑，有效地减小了结构的地震响应，保证了结构的安全。核电厂采用隔震技术后，核电厂房在结构在服役期间的抗震能力、场地和管道连接的适应性、结构和内部设备的易损性和可靠度依然是隔震核电厂发展所面临的关键技术。本项目建立了精细化的隔震和非隔震核电厂房模型，给出了核电厂在强震作用下的动力响应和变形特征，提出了隔震核电厂房柔性连接方式，揭示了隔震核电厂房的减震规律。利用任意拉格朗日欧拉流固耦合算法，参数化研究重力水箱不同水位的流固耦合效应及其对核电厂房的减震效应，提出了核电厂房重力水箱内部挡板设计方案，研究了不同挡板的减震效应，给出了重力水箱挡板的最优设计方案。基于IDA并考虑土-地基的相互作用，采用应变准则，建立核电厂房的极限状态方程，给出了隔震和非隔震核电厂房的地震易损性，揭示了不同强度地震动作用下核电厂房地震响应特征和功能失效机理，获得了核电厂房的破坏状态和各级破坏概率，揭示不同强度地震作用下隔震核电厂房及内部设备的失效概率和抗震可靠度，评估了隔震和非隔震核电厂房的概率安全。项目成果为隔震核电厂在我国的应用和推广提供理论和技术依据。