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AbstractAbstract
[en] Gas cooled high temperature reactor (HTR) belongs to the new generation of nuclear power plants called Generation IV. The Generation IV gathers the entire future nuclear reactors concept with an effective deployment by 2050. The technological choices relating to the nature of the fuel, the moderator and the coolant as well as the annular geometry of the core lead to some physical characteristics. The most important of these characteristics is the very strong thermal feedback in both active zone and the reflectors. Consequently, HTR physics study requires taking into account the strong coupling between neutronic and thermal hydraulics. The work achieved in this Phd consists in modeling, programming and studying of the neutronic and thermal hydraulics coupling system for block type gas cooled HTR. The coupling system uses a separate resolution of the neutronic and thermal hydraulics problems. The neutronic scheme is a double level Transport (APOLLO2) /Diffusion (CRONOS2) scheme respectively on the scale of the fuel assembly and a reactor core scale. The thermal hydraulics model uses simplified Navier Stokes equations solved in homogeneous porous media in code CAST3M CFD code. A generic homogenization model is used to calculate the thermal hydraulics parameters of the porous media. A de-homogenization model ensures the link between the porous media temperatures of the temperature defined in the neutronic model. The coupling system is made by external procedures communicating between the thermal hydraulics and neutronic computer codes. This Phd thesis contributed to the Very High Temperature Reactor (VHTR) physics studies. In this field, we studied the VHTR core in normal operating mode. The studies concern the VHTR core equilibrium cycle with the control rods and using the neutronic and thermal hydraulics coupling system. These studies allowed the study of the equilibrium between the power, the temperature and Xenon. These studies open new perspective for core optimization and design. (author)
Original Title
Modelisation globale des reacteurs a caloporteur gaz de generation-4: application au Very High Temperature Reactor (VHTR)
Primary Subject
Source
Dec 2006; 176 p; 78 refs; Also available from Bibliotheque universitaire d'Evry Val d'Essonne, 2 rue Andre Lalande, 91025 - Evry Cedex (France); These energetique
Record Type
Report
Literature Type
Thesis/Dissertation
Report Number
Country of publication
COMPUTER CODES, DIFFERENTIAL EQUATIONS, ENRICHED URANIUM REACTORS, EQUATIONS, EXPERIMENTAL REACTORS, FLUID MECHANICS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, HYDRAULICS, MECHANICS, PARTIAL DIFFERENTIAL EQUATIONS, POWER REACTORS, REACTORS, RESEARCH AND TEST REACTORS, SIMULATION, THERMAL REACTORS
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