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Ultimate analysis of PWR prestressed concrete containment subjected to internal pressure

机译:内压下PWR预应力混凝土安全壳的极限分析

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Numerical analyses are carried out by using the ABAQUS finite element program to predict the ultimate pressure capacity and the failure mode of the PWR prestressed concrete containment at Maanshan nuclear power plant. Material nonlinearity such as concrete cracking, tension stiffening, shear retention, concrete plasticity, yielding of prestressing tendon, yielding of steel reinforcing bar and degradation of material properties due to high temperature are all simulated with proper constitutive models. Geometric nonlinearity due to finite deformation has also been considered. The results of the analysis show that when the prestressed concrete containment fails, extensive cracks take place at the apex of the dome, the junction of the dome and cylinder, and the bottom of the cylinder connecting to the base slab. In addition, the ultimate pressure capacity of the containment is higher than the design pressure by 86 percent.
机译:利用ABAQUS有限元程序进行了数值分析,以预测马鞍山核电站PWR预应力混凝土安全壳的极限压力能力和破坏模式。材料非线性,如混凝土开裂,拉伸刚度,剪切保持力,混凝土可塑性,预应力筋的屈服,钢筋的屈服以及由于高温导致的材料性能退化,都可以通过适当的本构模型进行模拟。还考虑了由于有限变形而引起的几何非线性。分析结果表明,当预应力混凝土围护结构失效时,穹顶的顶点,穹顶与圆柱体的连接处以及圆柱体底部与基础板的连接处会发生大量裂纹。此外,安全壳的极限压力容量比设计压力高86%。

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