Mechanical consequences of LOCA in PWR: Full scale coupled 1D/3D simulations with fluid–structure interaction
| Autor: | Fabien Crouzet, F. Debaud, Vincent Faucher |
|---|---|
| Přispěvatelé: | Laboratoire d'études de DYNamique (DYN), Service d'Etudes Mécaniques et Thermiques (SEMT), Département de Modélisation des Systèmes et Structures (DM2S), CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay-Département de Modélisation des Systèmes et Structures (DM2S), Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Commissariat à l'énergie atomique et aux énergies alternatives (CEA)-Université Paris-Saclay |
| Rok vydání: | 2014 |
| Předmět: |
Nuclear and High Energy Physics
Engineering business.industry Mechanical Engineering Nuclear engineering Pressurized water reactor Flow (psychology) Full scale Structural engineering law.invention [SPI]Engineering Sciences [physics] Nuclear Energy and Engineering Nuclear reactor core law Fluid–structure interaction General Materials Science Transient (oscillation) Safety Risk Reliability and Quality business Representation (mathematics) Waste Management and Disposal Loss-of-coolant accident |
| Zdroj: | Nuclear Engineering and Design Nuclear Engineering and Design, 2014, 270, pp.359-378. ⟨10.1016/j.nucengdes.2014.02.008⟩ |
| ISSN: | 0029-5493 1872-759X |
| DOI: | 10.1016/j.nucengdes.2014.02.008 |
| Popis: | International audience; 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. |
| Databáze: | OpenAIRE |
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