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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.

La thèse s’inscrit dans le cadre industriel de la détection de la réaction entre l’eau et le sodium dans un générateur de vapeur d’un réacteur à neutrons rapides à caloporteur sodium. Plus précisément, il s’agit de détecter une micro-fuite d’eau dans le sodium (débit < 1 g/s) en moins de 10 secondes à partir des signaux vibratoires mesurés sur la virole externe du générateur de vapeur. Le bruit de fond très important de l’installation en fonctionnement risque de mettre en défaut la détection basée sur un dépassement de seuil de l’énergie vibratoire. Nous nous intéressons dans cette thèse à la technique de la formation de voies qui permet d’augmenter le rapport signal à bruit et de détecter et de localiser une source acoustique à l’intérieur du système à partir de signaux vibratoires mesurés par une antenne de capteurs accéléromètres placés sur la coque cylindrique (i.e. virole du générateur de vapeur). Une étude numérique a d’abord été réalisée. Des modèles numériques sont développés afin de simuler les signaux mesurés (virtuellement) par les accéléromètres de l’antenne linéaire considérée. Les performances de la formation de voies sont alors étudiées suivant différents paramètres (i.e. position source, amortissement, fréquence, type de bruit de fond, etc.). Le premier modèle consiste en une plaque plane infinie en contact avec un fluide lourd et excitée par un monopole acoustique situé dans ce fluide. L’analyse des déplacements transverses de la plaque nous permet d’établir un critère sur l’échantillonnage spatial du champ vibratoire par l’antenne. Un second modèle, plus représentatif de la virole du générateur de vapeur, est ensuite proposé. Une coque cylindrique élastique infinie, remplie par un fluide lourd est considérée. Le caractère « fini » de ce système dans les directions radiales et circonférentielles fait apparaitre un comportement modal. Son impact sur la formation de voies est étudié. La méthode est finalement testée expérimentalement. Des mesures sont réalisées sur une maquette composée d’un cylindre en acier rempli d’eau, placé dans un circuit hydraulique dont on maitrise le débit. La source acoustique est générée à partir d’un hydrophone. On étudie alors le gain d’antenne pour différents débits et niveaux d’excitation de la source. / This thesis deals with a new method to detect a sodium-water reaction in a steam generator of a fast sodium-cooled nuclear reactor. More precisely, the objective is to detect a micro-leak of water (flow < 1 g/s) in less than 10 seconds by measuring the external shell vibrations of the component. The strong background noise in operation makes impossible the use of a detection system based on a threshold overrun. A beamforming method applied to vibrations measured by a linear array of accelerometers is developed in this thesis to increase the signal-to-noise ratio and to detect and locate the leak in the steam generator. A numerical study is first realized. Two models are developed in order to simulate the signals measured by the accelerometers of the array. The performances of the beamforming are then studied in function of several parameters, such as the source location and frequency, the damping factor, the background noise considered. The first model consists in an infinite plate in contact with a heavy fluid, excited by an acoustic monopole located in this fluid. Analyzing the transverse displacements in the wavenumber domain is useful to establish a criterion to sample correctly the vibration field of the plate. A second model, more representative of the system is also proposed. In this model, an elastic infinite cylindrical shell, filled with a heavy fluid is considered. The finite dimensions in the radial and circumferential directions lead to a modal behavior of the system which impacts the beamforming. Finally, the method is tested on an experimental mock-up which consists in a cylindrical pipe made in stainless steel and filled with water connected to hydraulic circuit. The water flow speed can be controlled by varying the speed of the pump. The acoustic source is generated by a hydrophone. The performances of the beamforming are studied for different water flow speeds and different amplitude and frequencies of the source.

abstract: ABSTRACT The heat recovery steam generator (HRSG) is a key component of Combined Cycle Power Plants (CCPP). The exhaust (flue gas) from the CCPP gas turbine flows through the HRSG &#8722; this gas typically contains a high concentration of NO and cannot be discharged directly to the atmosphere because of environmental restrictions. In the HRSG, one method of reducing the flue gas NO concentration is to inject ammonia into the gas at a plane upstream of the Selective Catalytic Reduction (SCR) unit through an injection grid (AIG); the SCR is where the NO is reduced to N2 and H2O. The amount and spatial distribution of the injected ammonia are key considerations for NO reduction while using the minimum possible amount of ammonia. This work had three objectives. First, a flow network model of the Ammonia Flow Control Unit (AFCU) was to be developed to calculate the quantity of ammonia released into the flue gas from each AIG perforation. Second, CFD simulation of the flue gas flow was to be performed to obtain the velocity, temperature, and species concentration fields in the gas upstream and downstream of the SCR. Finally, performance characteristics of the ammonia injection system were to be evaluated. All three objectives were reached. The AFCU was modeled using JAVA - with a graphical user interface provided for the user. The commercial software Fluent was used for CFD simulation. To evaluate the efficacy of the ammonia injection system in reducing the flue gas NO concentration, the twelve butterfly valves in the AFCU ammonia delivery piping (risers) were throttled by various degrees in the model and the NO concentration distribution computed for each operational scenario. When the valves were kept fully open, it was found that it led to a more uniform reduction in NO concentration compared to throttling the valves such that the riser flows were equal. Additionally, the SCR catalyst was consumed somewhat more uniformly, and ammonia slip (ammonia not consumed in reaction) was found lower. The ammonia use could be decreased by 10 percent while maintaining the NO concentration limit in the flue gas exhausting into the atmosphere. / Dissertation/Thesis / M.S. Mechanical Engineering 2011

The topic of thesis is condensing turbine in gas-steam cycle, which can be divided into four basic parts. A history of gas-steam cycle is described in the beginning. Second part is all about calculation of heat recovery steam generator. Penultimate section deals with calculations of steam turbine parameters and reaction blading type. Last part contains electric power and steam turbine efficiency.

The main aim of this thesis is the model design and control the secondary circuit block VVER 440. The search part of my work is a description of the secondary circuit. In the first part of the calculation is performed for the rated secondary circuit. The second calculation part focuses on the calculation circuit of the secondary for the reduced, influenced by shutting down one steam generator.

This master’s thesis deals with the design of a heat recovery steam generator. The introductory part of the thesis is dedicated to waste heat boilers, their division and their utilization in combined cycles gas turbine. In the following chapter, an analysis of the existing combined heat and power plant operation is performed. In the next part of the thesis, the conceptual layout of the new source is designed. Subsequently, the thermal calculation of the boiler is carried out as well as the design of individual heat exchanging surfaces. The sixth chapter deals with the strength calculation of the boiler and the outer piping, chambers and drum are designed here. At the end of the thesis there are described off-design states of the new combined cycle gas turbine.

The aim of this work is to analyze the methodology for executing examination heat transfer tubes of steam generator by method of eddy currents on EDU, to create the model for the estimate of standard combined uncertainty of efficiency value, quantify the individual components of standard uncertainties, analyse the influence of different components on the expressing of uncertainty, to make the final estimate of standard combined and enlarged uncertainty of efficiency value and as of minor objective to evaluate the suitability of the use of this method .

The target of this diploma thesis is design of cogeneration unit with following requirements: • Installation of new unit instead of the old and used up one. • Electric energy supply within Supportive service – fast starts • Greening (replacement of coal with natural gas) At the beginning I deal with the current state of old unit. In the next part there is the design of new technological unit, which consists of design of boilers, gas engines, steam turbines. Final phase of the thesis includes economical analysis focused on setting of financial return.

This master thesis deals steam generator for ESFR (European Sodium Fast Reactor), which is heated by liquid sodium. In the beginning chapters, there are theoretic information about ESFR's parameters and its' comparison with ohter types of heat exchangers in nuclear reactors with the same principal (sodium as a coolant). Then designing part follows, which contents of introduction of calculations, option of material and conception of heater. Computational part on its own includes thermal, hydraulic and stress calculations and comparison with aspects in nuclear safety and security.