摘要
对核电厂预应力混凝土安全壳结构进行了内压作用下的非线性有限元分析。详细介绍了ANSYS中的混凝土单元SOLID65及混凝土材料的本构关系,并对非线性求解过程中影响收敛的因素进行了分析;同时,以福清核电厂5、6号机组内层安全壳为工程实例进行有限元计算。结果表明,15 m至30 m标高范围内的径向位移大于其他高度的径向位移,标高25 m左右径向位移最大;内压加至O.42MPa,模型结构仍处于受压状态,满足使用要求。分析表明,福清核电厂5、6号机组安全壳结构在设计内压作用下是安全的,可为安全壳整体性试验提供参考。
Nonlinear finite element analysis of nuclear power plant prestressed concrete containment structure subjected to internal pressure is carried out. SOLID65 element and constitutive model of concrete in ANSYS are introduced in detail, and solution control methods are put forward. In numerical simula- tion, the radial displacement between 15m and 30m model height is larger than that at other level, and the radial displacement at about 25m height is the maximum. Because of prestressing, the model structure is under compression till internal pressure is up to 0. 42MPa, and it satisfies the design requirement. A- nalysis of the model structure shows that the containment is safe under the given inner pressure, which can contribute to the integrity test of concrete containment structure.
出处
《核安全》
2012年第2期21-24,F0003,共5页
Nuclear Safety
