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介绍秦山核电站预应力混凝土安全壳1∶10模型试验的主要结果及其与理论分析的比较。除进行内压破坏试验外,还利用该模型完成了模拟地震的拟动力试验和大开孔试验,取得了一大批重要的实测数据,为评价秦山及大亚湾核电站安全壳的安全性提供了重要的试验依据。证明该电站预应力混凝土安全壳有大约3倍于事故内压的极限承载力和能安全地经受0.15g的强烈地震,其设备大开孔的加强措施是安全的和合理的。此外,论证了非线性有限元分析程序的可靠性,为安全壳的设计提供了有效的理论分析手段。
The main results of the 1:10 model test of the prestressed concrete containment in Qinshan Nuclear Power Station are introduced and compared with the theoretical analysis. In addition to the internal pressure destruction test, the model was used to complete the pseudo-dynamic test and large-opening test of simulated earthquakes, and a large number of important measured data were obtained, which provided important indicators for evaluating the safety of the containment of Qinshan and Daya Bay nuclear power plants. Test basis. It was proved that the prestressed concrete containment of the power station had an ultimate bearing capacity of about 3 times the internal pressure of the accident and could withstand a strong earthquake of 0.15 g safely, and the strengthening measures for the large opening of the equipment were safe and reasonable. In addition, the reliability of the nonlinear finite element analysis program is demonstrated, and an effective theoretical analysis method is provided for the design of the containment vessel.