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

  • Ying Chao Ma
  • , Xie Lin Zhao
  • , Xian Hui Ye
  • , Nai Bin Jiang
  • , Jin Xiong Zhou
  • Xi'an Jiaotong University
  • Nuclear Power Institute of China
  • Sun Yat-Sen University

Research output: Contribution to journalArticlepeer-review

5 Scopus citations

Abstract

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.

Original languageEnglish
Article number54
JournalNuclear Science and Techniques
Volume31
Issue number6
DOIs
StatePublished - 1 Jun 2020

Keywords

  • Finite element method
  • Fluid–structure interaction (FSI)
  • Loss-of-coolant accident (LOCA)
  • Prestressed structure
  • Structural dynamics

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