点击次数：

发表时间：2022-10-04

发表刊物：哈尔滨工程大学学报

所属单位：建设工程学部

期号：2

页面范围：162-167

ISSN号：1006-7043

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.

备注：新增回溯数据