<p>Among the six GEN-IV reactor concepts recommended by the Gen-IV International Forum, supercritical water-cooled reactors (SCWR) have gained significant interests due to its economic advantage, technology and experience continuity. In the last few years, extensive R&D activities have been launched covering the various aspects of SCWR development, especially in thermal-hydraulic analysis. In Canada, most R&D projects are led by AECL or NRCan.</p> <p>SCWR design and development require the modification of simulation codes used for design and safety demonstration of subcritical water-cooled reactors. This study modifies the subchannel code COBRA-TF, applicable to only subcritical water-cooled reactors, to a new version COBRA-TF-SC, applicable to both supercritical and subcritical water-cooled reactors. Supercritical water property data tables and supercritical water property formulations are implemented. Supercritical water heat transfer and pressure drop correlations are also added. The saturation curve in the subcritical model is extended by introducing a pseudo two-phase region at supercritical pressures to avoid any numerical instabilities consistent with other studies.</p> <p>Some simple fuel bundle experimental data on the flow and temperature distribution are used to evaluate the code. The fuel bundle experiment is simulated with both COBRA-TF-SC and AECL's ASSERT-PV-SC. The COBRA-TF-SC predicted results show good agreement with the experimental data and results obtained from ASSERT-PV-SC, demonstrating good feasibility and accuracy of this code. COBRA-TF-SC is then used to predict the detailed thermalhydraulics behaviour of the 62-element Canadian SCWR fuel bundle design. The advantage of COBRA-TF-SC is that it can accommodate transcritical flow conditions whereas the existing subchannel codes for SCWRs cannot.</p> / Master of Applied Science (MASc)

Ce travail de thèse s'inscrit dans le cadre d'un projet de recherche industriel visant à améliorer les méthodes et les outils de simulation du comportement thermohydraulique et vibratoire dans les générateurs de vapeur des centrales nucléaires, en présence de colmatage. Le colmatage des générateurs de vapeur est un phénomène de déposition de matières au niveau d'interstices, appelés passages foliés, qui perturbe la libre circulation de l'écoulement appartenant au circuit secondaire. L'objectif de ces travaux de thèse est de disposer d'un modèle permettant de simuler ce phénomène dans l'intégralité du générateur de vapeur à l'échelle du sous-canal du faisceau de tubes. Le modèle proposé se décompose en deux étapes au niveau de chaque passage folié : une étape de déposition des particules, et une étape de consolidation du dépôt par précipitation d'espèces solubles. Une méthode inverse d'assimilation de données a été développée pour ajuster ce modèle sur les différentes observations issues du retour d'expérience disponible à EDF. Les résultats de simulation sont comparables aux données mesurées sur sites d'exploitation pour les générateurs de vapeur étudiés. L'impact du colmatage sur l'écoulement se caractérise par l'apparition de survitesses en partie supérieure du générateur de vapeur à l'origine d'instabilités vibratoires des tubes, et par la diminution du taux de recirculation. Par ailleurs, les résultats de simulation confirment qu'une augmentation du pH dans l'ensemble du circuit secondaire semble une solution intéressante pour atténuer le phénomène de colmatage. Ce remède est actuellement envisagé sur le parc nucléaire français. / In nuclear power plants, corrosion product deposits in the secondary side of steam generators may result in tube support plate flow blockage. Flow blockage is a deposit at the inlet of tube support plate flow holes. It may induce high velocity zones in the secondary flow, then vibrations and tube cracks in some cases. The main objective of this work is to model and simulate this deposit phenomenon in the whole steam generator. A new deposit model has been also developed and implemented in the frame of THYC. THYC is the EDF's reference code for the modelling of 3D two-phase thermal-hydraulic phenomena at the subchannel scale. The deposit model is defined by two main steps : particle deposition, and strengthening process due to soluble species precipitation in the pores of particle deposits. It is calibrated on blockage rates observed in steam generators using an inverse method also developed in this work. The relevance of this model is tested by comparing the simulation results to the actual levels of flow blockage observed in some nuclear plants. The main impact of flow blockage on the secondary flow is localized at the upper tube support plate and may induce tube vibrations. Moreover the simulation results underline the pH dependence of flow blockage phenomenon. A pH elevation of the secondary flow is one of the remedies currently considered on EDF's nuclear fleet.

Orthogonal frequency division multiplexing (OFDM) in next generation wireless systems provides high downlink data rates by employing frequency-domain scheduling and rate adaptation at the base station (BS). However, in order to control the significant feedback overhead required by these techniques, feedback reduction schemes are essential. Best-m feedback is one such scheme that is implemented in OFDM standards such as Long Term Evolution. In it, the sub channel (SC) power gains of only the m strongest SCs and their corresponding indices are fed back to the BS. However, two assumptions pervade most of the literature that analyze best-m feedback in OFDM systems. The first one is that the SC gains are uncorrelated. In practice, however, the SC gains are highly correlated, even for dispersive multipath channels. The second assumption deals with the treatment of unreported SCs, which are not fed back by the best-m scheme. If no user reports an SC, then no data transmission is assumed to occur. In this thesis, we eschew these assumptions and investigate best-m feedback in OFDM systems with correlated SC gains. We, first, characterize the average throughput as a function of correlation and m. A uniform correlation model is assumed, i.e., the SC gains are correlated with each other by the same correlation coefficient. The system model incorporates greedy, modified proportional- fair, and round robin schedulers, discrete rate adaptation, and non-identically distributed SC gains of different users. We, then, generalize the model to account for feedback delay. We show in all these cases that correlation degrades the average throughput. We also show that this effect does not arise when users report all the SC power gains to the BS. In order to mitigate the reduction in the average throughput caused by unreported SCs, we derive a novel, constrained minimum mean square error channel estimator for the best-m scheme to estimate the gains of these unreported SCs. The estimator makes use of the additional information, which is unique to the best-m scheme, that the estimated SC power gains must be less than those that were reported. We, then, study its implications on the downlink average cell throughput, again for different schedulers. We show that our approach reduces the root mean square error and increases the average throughput compared to several approaches pursued in the literature. The more correlated the SC gains, greater is the improvement.