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AbstractAbstract
[en] In the case of PWR severe accident (Loss of Coolant Accident, LOCA), the inner containment ambient properties such as temperature, pressure and gas species concentrations due to the released steam condensation are the main factors that determine the risk. For this reason, their distributions should be known accurately, but the complexity of the geometry and the computational costs are strong limitations to conduct full three-dimensional numerical simulations. An alternative approach is presented in this thesis, namely, the coupling between a lumped-parameter model and a CFD. The coupling is based on the introduction of a 'heat transfer function' between both models and it is expected that large decreases in the CPU-costs may be achieved. First of all, wall condensation models, such as the Uchida or the Chilton-Colburn models which are implemented in the code CAST3M/TONUS, are investigated. They are examined through steady-state calculations by using the code TONUS-0D, based on lumped parameter models. The temperature and the pressure within the inner containment are compared with those reported in the archival literature. In order to build the 'heat transfer function', natural convection heat transfer is then studied by using the code CAST3M for a partitioned cavity which represents a simplified geometry of the reactor containment. At a first step, two-dimensional natural convection heat transfer without condensation is investigated only. Either the incompressible-Boussinesq fluid flow model or the asymptotic low Mach model are considered for solving the time dependent conservation equations. The SUPG finite element method and the implicit scheme are applied for the numerical discretization. The computed results are qualified by the second-order Richardson extrapolation method which allows obtaining the so-called 'Exact values', i.e. grid size independent values. The computations are also validated through non-partitioned cavity case studies. The discussion is focused on heat transfer characteristics such as the variations of the average Nusselt number (Nu-bar) versus the dimensionless thickness of the partition (0.01 ≤ γ ≤ 0.2) and conductivity ratio of the partition wall to the fluid (1 ≤ σ ≤ 105). Finally, a 'heat transfer function' is suggested based upon the thermal resistance of the partition wall. The validity of the model is assessed thanks to comparisons with 'half-cavity' simulations. (author)
Original Title
Etude numerique 0D-multiD pour l'analyse de perte de refrigerant dans une enceinte de confinement d'un reacteur nucleaire
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Source
Dec 2005; 263 p; 78 refs.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS-NKM website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/. Also available from Universite Paris-Est Marne-la-Vallee. Bibliotheque, 5 Bd. Descartes Champs-sur-Marne, 77454 - Marne-la-Vallee CEDEX 02 (France); These thermique et systeme energetique
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Report
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Thesis/Dissertation
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