内压荷载下安全壳1:10模型结构非线性有限元分析
NONLINEAR FINITE ELEMENT ANALYSIS OF 1:10 CONTAINMENT MODEL STRUCTURE SUBJECTED TO INTERNAL PRESSURE
-
摘要: 对先进核电厂预应力混凝土安全壳1:10模型结构进行了内压作用下的非线性有限元分析。径向位移计算值与实验值的比较说明了计算模型和计算参数基本合理;由于预应力的作用,内压加至0.6MPa,模型结构仍处于受压状态,满足使用要求;1.5m至3.0m高范围内的径向位移大于其它高度的径向位移,标高2.0m左右的径向位移最大;沿模型结构环向,63.24°附近的径向位移大于其它位置的径向位移;极限内压为1.34MPa,为设计内压的3.35倍。分析表明,新开发的先进核电厂安全壳结构在内压作用下是安全的。Abstract: Nonlinear finite element analysis of 1:10 advanced nuclear power plant prestressed concrete containment model structure subjected to internal pressure is carried out. Comparison between the analytical radial displacements and the experimental radial displacements shows that the analytical model and parameters are reasonable. Because of prestressing, the model structure is under compression till internal pressure is up to 0.6MPa, and it satisfies the design requirement. The radial displacement between 1.5m and 3.0m model height is larger than that at other level, and the radial displacement at about 2.0m height is the maximum. The radial displacement near 63.24° section along model circle is larger than that at other sections. Ultimate inner pressure of the model structure is 1.34MPa, and is 3.35 times of the design value. Analysis of the model structure shows that the newly developed containment is safe under the given inner pressure.