A transient fluid–structure interaction analysis strategy and validation of a pressurized reactor with regard to loss-of-coolant accidents

Nuclear Science and Techniques(2020)

引用 0|浏览2
暂无评分
摘要
A loss-of-coolant accident (LOCA) is one of the basic design considerations for nuclear reactor safety analysis. A LOCA induces propagation of a depressurization wave in the coolant, exerting hydrodynamic forces on structures via fluid–structure interaction (FSI). The analysis of hydrodynamic forces on the core structures during a LOCA process is indispensable. We describe the implementation of a numerical strategy for prestressed structures. It consists of an initialization and a restarted transient analysis process, all implemented via the ANSYS Workbench by system coupling of ANSYS and Fluent. Our strategy is validated by making extensive comparisons of the pressures, displacements, and strains on various locations between the simulation and reported measurements. The approach is appealing for dynamic analysis of other prestressed structures, owing to the good popularity and acknowledgement of ANSYS and Fluent in both academia and industry.
更多
查看译文
关键词
Loss-of-coolant accident (LOCA),Fluid–structure interaction (FSI),Finite element method,Prestressed structure,Structural dynamics
AI 理解论文
溯源树
样例
生成溯源树,研究论文发展脉络
Chat Paper
正在生成论文摘要