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Modelling Pressurized Water Reactor cores in terms of porous media
Authors:G Ricciardi  S Bellizzi  B Collard  B Cochelin
Institution:1. CEA CADARACHE DEN/DTN/STRI/LHC, 13108 Saint-Paul-Lez-Durance Cedex, France;2. LMA CNRS, 31 chemin Joseph Aiguier, 13402 Marseille Cedex 20, France;1. Centro de Ciências e Tecnologias Nucleares, Instituto Superior Técnico, Universidade de Lisboa, Estrada Nacional 10, Km 139.7, 2695-066 Bobadela LRS, Portugal;2. CEA, DEN, DM2S, SEMT, Laboratoire d’Etudes de Dynamique, F-91191 Gif-Sur-Yvette, France
Abstract:The aim of this study is to develop a tractable model of a nuclear reactor core taking the complexity of the structure (including its nonlinear behaviour) and fluid flow coupling into account. The mechanical behaviour modelling includes the dynamics of both the fuel assemblies and the fluid. Each rod bundle is modelled in the form of a deformable porous medium; then, the velocity field of the fluid and the displacement field of the structure are defined over the whole domain. The fluid and the structure are first modelled separately, before being linked together. The equations of motion for the structure are obtained using a Lagrangian approach and, to be able to link up the fluid and the structure, the equations of motion for the fluid are obtained using an arbitrary Lagragian Eulerian approach. The finite element method is applied to spatially discretize the equations. Simulations are performed to analyse the effects of the characteristics of the fluid and of the structure. Finally, the model is validated with a test involving two fuel assemblies, showing good agreement with the experimental data.
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