内压作用下CP R1000安全壳的破坏机理研究

摘要

The containment vessel of a nuclear reactor is the last barrier to prevent leaks of radioactive substance in a nuclear power plant. It should be able to withstand the internal pressure with no concrete cracks appearing during a loss-of-coolant accident. This paper takes CPR1000 containment vessel as the research object, and a 3D nonlin⁃ear finite element numerical model is established according to the practical condition of prestressed tendons. This paper discussed simulation method of interaction between prestressed tendon and concrete, and compared internal force of prestressed tendon before and after the internal pressure is added to the containment vessel, which has veri⁃fied the correctness of the method proposed in this paper. This paper has given the damage mode and weak parts of containment vessel under the action of internal pressure, which provides a basis for analysis and design of the con⁃tainment vessel.%核反应堆安全壳是核电厂中防止放射性物质外泄的最后一道屏障，在发生LOCA 等设计基准事故时，若安全壳承受的内压不超过设计压力，安全壳混凝土不应出现裂缝。以实际CPR1000安全壳为研究对象，按照预应力筋实际情况建立三维非线性有限元数值模型，着重探讨了安全壳中预应力筋与混凝土之间相互作用的模拟方法，分析了安全壳施加内压前后预应力筋内力变化情况，验证了本文所提方法的准确性。给出了安全壳在内压作用下的破坏模式和薄弱部位，为安全壳的分析和设计提供依据。