核电厂安全壳结构钢衬里力学行为研究进展

Research Progress of Steel Liner Behavior in Nuclear Containment Structure

钢衬里作为核电厂安全壳结构的重要防泄漏部件,对保证核电厂安全运行及人员安全至关重要。本文从试验研究,数值模拟分析以及理论分析三方面对钢衬里力学行为相关研究进行系统总结。综合国外著名安全壳模型试验结果,阐述了钢衬里在事故压力荷载下的撕裂机理。详细对比多轴应力状态系数的不同计算方法,同时指出目前关于钢衬里力学行为问题研究不足及需要深入研究的问题。通过文献综述对比发现:局部区域变形集中是造成钢衬里撕裂的主要原因,钢衬里局部连接几何条件、锚固系统以及钢衬里与混凝土之间相互作用是影响钢衬里撕裂的主要因素。三种钢衬里撕裂准则对应考虑的影响因素不尽相同,钢衬里多轴应力状态系数三种计算方法差别较大,综合相关钢衬里撕裂判定准则研究成果,提出了建议的钢衬里撕裂准则,且本文建议的钢衬里撕裂准则与美国核管会导则RG.1.216准则吻合程度很好。此外,深化钢衬里撕裂机理研究,在此基础上发展安全壳泄漏概率安全评价方法是后续研究工作的重点。

As an important leak-proof component for nuclear containment structure in nuclear power plant,steel liner plays a vital role in ensuring the safe operation of nuclear power plant and the safety of personnel.This study systematically summarizes the related studies on the steel liner mechanical behavior from three aspects:experimental study,numerical simulation analysis and theoretical analysis.Based on the well-known model test results of nuclear containment structure at abroad,the tearing mechanism of the steel liner under accidental pressure is clarified.Detailed comparison of different calculation methods for the multi-axial stress state factor is performed.At the same time,drawbacks of studies on the steel liner and the problems needing further study are pointed out.Through literature review and comparison,it is found that the main causes of tearing of the steel liner are concentrated deformation at local area.Geometrical conditions for local connection of the steel liner,the anchorage system and the interaction between the steel liner and concrete are the main factors affecting tearing of the steel liner.Factors which influence the steel liner tearing considered in three steel liner tearing calculation methods are not the same,and multi-axial stress factor is significantly different.An steel liner tearing criteria is proposed.The suggested liner tearing criteria is in good agreement with the criteria provided in the US NRC regulatory guide RG1.216.In addition,further study on the steel liner tearing mechanism and corresponding nuclear containment structure leakage evaluation method is the focus of future studies.