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Journal Articles Nuclear Engineering and Design Year : 2014

Mechanical consequences of LOCA in PWR: Full scale coupled 1D/3D simulations with fluid–structure interaction

F. Crouzet
  • Function : Author
F. Debaud
  • Function : Author

Abstract

The present paper is dedicated to the analysis of the fast transient mechanical consequences of the Loss Of Coolant Accident (LOCA) on the internal structures of a Pressurized Water Reactor (PWR). A complete methodology is described, based on a coupled 1D/3D representation of the entire primary loop of the reactor, with a robust and accurate approach for fluid–structure interaction inside the main vessel. A special attention is given to the modeling of small geometric details, such as perforated plates in the vicinity of the reactor core, through local impedance relations acting on the flow, which must be carefully calibrated for industrial purposes. The capabilities of the proposed framework are demonstrated with the application of the complete computational scheme to the simulation of the consequences of LOCA for a French 900 MW PWR, performed with EUROPLEXUS software.
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Dates and versions

cea-03979998 , version 1 (09-02-2023)

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V. Faucher, F. Crouzet, F. Debaud. Mechanical consequences of LOCA in PWR: Full scale coupled 1D/3D simulations with fluid–structure interaction. Nuclear Engineering and Design, 2014, 270, pp.359-378. ⟨10.1016/j.nucengdes.2014.02.008⟩. ⟨cea-03979998⟩

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