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Neutronics-Thermalhydraulics Coupling in a CANDU SCWR

Pierre Adouki

Master's thesis (2012)

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Abstract

In order to implement new nuclear technologies as a solution to the growing demand forenergy, 10 countries agreed on a framework for international cooperation in 2002, to formthe Generation IV International Forum (GIF). The goal of the GIF is to design the nextgeneration of nuclear reactors that would be cost effective and would enhance safety. Thisforum has proposed several types of Generation IV reactors including the SupercriticalWater-Cooled Reactor (SCWR). The SCWR comes in two main configurations: pressure vesselSCWR and pressure tube SCWR (PT-SCWR). In this study, the CANDU SCWR (a PTSCWR)is considered. This reactor is oriented vertically and contains 336 channels with alength of 5 m. The target coolant inlet and outlet temperatures are 350 Celsius and 625Celsius, respectively. The coolant flows downwards, and the reactor power is 2540 MWth.Various fuel designs have been considered in order not to exceed the linear element rating.However, the dependency between the core power and thermalhydraulics parameters resultsin the necessity to use a neutronics/thermalhydaulics coupling scheme to determine the corepower and the thermalhydraulics parameters. The core power obtained has a power peakingfactor of 1.4. The bundle power distribution for all channels has a peak at the third bundlefrom the inlet, but the value of this peak increases with the channel power. The heat-transfercoefficient and the specific-heat capacity have a peak at the same location in a channel,and this location shifts toward the inlet as the channel power increases. The exit coolanttemperature increases with the channel power, while the exit coolant density and pressuredecrease with the channel power. Also, higher channel powers lead to higher fuel and claddingtemperatures. Moreover, as the coupling method is applied, the effective multiplication factorand the values of thermalhydaulics parameters oscillate as they converge.

Résumé

Le but de ce travail est de déterminer la distribution de puissance et les paramètres thermohydrauliquespour un réacteur CANDU SCWR, par un couplage neutronique-thermohydraulique.La distribution de puissance obtenue a un facteur de puissance de 1.4. Chaque canal a unmaximum de puissance à la troisième grappe (à partir de l'entrée du canal), et cette valeurmaximale augmente avec la puissance du canal. Le coefficient de transfère thermique et lachaleure spécifique atteingnent leur valeur maximale à la même position dans un canal, etcette position se déplace vers l'entrée du canal en raison d'une augmentation de puissance decanal. La température de sortie du caloporteur augmente avec la puissance du canal, tandisque la pression et la densité de sortie diminuent avec l'augmentation de la puissance du canal.L'augmentation de la puissance du canal résulte aussi en des températures élevées pour lecombustible et la gaine. Le facteur de multiplication et les paramètres thermohydrauliquesoscillent autours de leurs valeurs à la convergence.
Department: Department of Engineering Physics
Program: Génie énergétique
Academic/Research Directors: Guy Marleau
PolyPublie URL: https://publications.polymtl.ca/946/
Institution: École Polytechnique de Montréal
Date Deposited: 14 Nov 2012 15:10
Last Modified: 12 Nov 2022 06:26
Cite in APA 7: Adouki, P. (2012). Neutronics-Thermalhydraulics Coupling in a CANDU SCWR [Master's thesis, École Polytechnique de Montréal]. PolyPublie. https://publications.polymtl.ca/946/

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