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Couplage 3D neutronique thermohydraulique. Développement d'outils pour les études de sûreté des réacteurs innovants

Abstract : Nuclear reactors are complex systems and modelling of their behaviour involves several sub-disciplines of physics. The most important are the neutronics, which governs the neutron transport and chain reaction in the core, and thermo-hydraulics, which treats the fluid flow of the coolant and the heat transfer from the fuel. These two different physical phenomena are coupled in reactor cores in a complex way : The fission chain reaction affects the heat produced and hence fuel and coolant temperatures and densities, and in turn, these affect the cross sections for the nuclear reactions. Thanks to the massive growth in computer power over the last few decades it is only now that it is possible to imagine to simulate this phenomenological complexity in a reasonable time. For this reason stochastic neutronics codes of the ”Monte-Carlo” type are used much more widely than in the past. They offer the great advantage of the ability of this type of probabilistic code resides in their ability to reproduce to ”faithfully” re-produce reality without recourse to modeling approximations. It is in this context that the following thesis work has been performed : a generic coupling of a Monte-Carlo based neutronics code to a thermo-hydraulics code to ensure the most accurate 3-dimensional description possible of operating conditions in a reactor core. This work is driven by the new demands for future reactor generations of increased security, the optimization of natural resources and the minimization of nuclear waste production. This manuscript presents the methodology for the development of an automated external coupling between the Monte Carlo based neutron transport code, MCNP, and the thermo-hydraulique/thermique code, COBRA-EN. The development these new and high precision simulation tools was accompanied with new physical-numeric problems which had to be solved. The problems encountered are highlighted in the manuscript. Finally, the validation of the coupled scheme was carried out on a complex, heterogenous benchmark in order to prove the robustness of the code developments undertaken and the feasibility of such a coupling
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Submitted on : Monday, April 19, 2010 - 5:31:42 PM
Last modification on : Wednesday, September 16, 2020 - 4:08:24 PM
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  • HAL Id : tel-00474353, version 1



N. Capellan. Couplage 3D neutronique thermohydraulique. Développement d'outils pour les études de sûreté des réacteurs innovants. Physique Nucléaire Théorique [nucl-th]. Université Paris Sud - Paris XI, 2009. Français. ⟨tel-00474353⟩



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