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A transient fiuid–structure interaction analysis strategy and validation of a pressurized reactor with regard to loss-ofcoolant accidents 被引量:1
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作者 Ying-Chao Ma xie-lin zhao +2 位作者 Xian-Hui Ye Nai-Bin Jiang Jin-Xiong Zhou 《Nuclear Science and Techniques》 SCIE CAS CSCD 2020年第6期11-21,共11页
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 struct... 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 viafiuid–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. 展开更多
关键词 Loss-of-coolant accident(LOCA) Fluid–structure interaction(FSI) Finite element method Prestressed structure Structural dynamics
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