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Dynamics of the free surface of stratified two-phase flows in channels with rectangular cross-sectionsVallée, Christophe 24 April 2012 (has links) (PDF)
Stratified two-phase flows were investigated at different test facilities with horizontal test sections in order to provide an experimental database for the development and validation of computational fluid dynamics (CFD) codes. These channels were designed with rectangular cross-sections to enable optimal observation conditions for the application of optical measurement techniques. Consequently, the local flow structure was visualised with a high-speed video camera, delivering data with high-resolution in space and time as needed for CFD code validation.
Generic investigations were performed at atmospheric pressure and room temperature in two air/water channels made of acrylic glass. Divers preliminary experiments were conducted with various measuring systems in a test section mounted between two separators. The second test facility, the Horizontal Air/Water Channel (HAWAC), is dedicated to co-current flow investigations. The hydraulic jump as the quasi-stationary discontinuous transition between super- and subcritical flow was studied in this closed channel. Moreover, the instable wave growth leading to slug flow was investigated from the test section inlet. For quantitative analysis of the optical measurements, an algorithm was developed to recognise the stratified interface in the camera frames, allowing statistical treatments for comparison with CFD calculation results.
The third test apparatus was installed in the pressure chamber of the TOPFLOW test facility in order to be operated at reactor typical conditions under pressure equilibrium with the vessel atmosphere. The test section representing a flat model of the hot leg of the German Konvoi pressurised water reactor (PWR) scaled at 1:3 is equipped with large glass side walls in the region of the elbow and of the steam generator inlet chamber to allow visual observations. The experiments were conducted with air and water at room temperature and maximum pressures of 3 bar as well as with steam and water at boundary conditions of up to 50 bar and 264°C. Four types of experiments were performed, including generic test cases as well as transient validation cases of typical nuclear reactor safety issues. As an example, the co-current flow experiments simulate the two-phase natural circulation in the primary circuit of a PWR. The probability distribution of the water level measured in the reactor pressure vessel simulator was used to characterise the flow in the hot leg. Moreover, the flooding behaviour in this conduit was investigated with dedicated counter-current flow limitation experiments. A comparison of the flooding characteristics with similar experimental data and correlations available in the literature shows that the channel height is the characteristic length to be used in the Wallis parameter for channels with rectangular cross-sections. Furthermore, for the analysis of steam/water experiments, condensation effects had to be taken into account. Finally, the experimental results confirm that the Wallis similarity is appropriate to scale flooding in the hot leg of a PWR over a large range of pressure and temperature conditions.
Not least, different examples of comparison between experiment and simulation demonstrate the possibilities offered by the data to support the development and validation of CFD codes. Besides the comparison of qualitative aspects, it is shown exemplarily how to treat the CFD results in order to enable quantitative comparisons with the experiments.
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Experimentelle Untersuchung der Thermofluiddynamik bei der Kontaktkondensation von Dampf an unterkühlter Flüssigkeit in einem weiten DruckbereichSeidel, Tobias 20 February 2020 (has links)
Verlässliche Vorhersagen zum Verlauf von Störfallszenarien in Reaktorsystemen sind mit CFD-Modellen möglich, wenn diese anhand von Experimenten entwickelt und validiert sind. Motiviert durch die Vorgänge, die bei einem Thermoshock-Szenario unter Druck im Primärkreis eines Druckwasserreaktors entstehen, wurden im Rahmen dieser Arbeit Experimente zur Direktkontaktkondensation von Dampf an unterkühltem Wasser bei hohen Drücken untersucht.
Der beschriebene Versuchsaufbau erlaubt es, in einer Anlage, die drei Phänomene geschichtete Strömung, Strahl und Blasenmitriss zu untersuchen. Eine umfassende Instrumentierung ermöglichte es, besonders viele Informationen aus den Experimenten zu erfassen. Verschiedene bildgebende Messverfahren erlauben einen besonderen Einblick in die Strömung ohne Rückkopplung ins Fluid zu haben. Einzelne Mess- und Auswertemethoden wurden extra für die Untersuchung entwickelt und beschrieben.
Vor Allem die Messergebnisse der Strahlexperimente mit Kondensation sind umfangreich und neuartig. Die starke Turbulenz im Inneren der untersuchten Strahlen führen zu den höchsten Kondensationsraten in den vorliegenden Experimenten. Hier wurden die Strahldurchmesser-Verläufe für verschiedene Randbedingungen verglichen, um zu zeigen, wie stark die Kondensation an Strahlen vom Umgebungsdruck abhängt.
Die Gas-Mitriss-Experimente sind die ersten dokumentierten Versuche dieser Art. Sie zeigen, dass das mitgerissene Gas bei Eintrittsunterkühlungen oberhalb von 10 K sofort an der Eintrittsstelle kondensiert. Es kommt nicht zur Bildung von Blasen oder zum Mitriss nach unten. Vielmehr ist ausschließlich ein negativer Meniskus zu erkennen, der eine von den Randbedingungen abhängige Geometrie hat. Je geringer die Eintritts-Unterkühlung und je höher die Strahlgeschwindigkeit ist, desto tiefer dringt der Gas-Meniskus in die Wasservorlage ein. Die Menge an mitgerissenem Gas ist auch bei hohen Geschwindigkeiten klein gegenüber der Kondensationsmenge am Strahl.
Die Experimente wurden im Wesentlichen darauf ausgelegt, Daten für den Vergleich mit CFD-Simulationen zu liefern. Vor allem der Einfluss des Umgebungsdruckes auf die Strahlgeometrie und die Kondensationsrate sollte weiter untersucht und in Simulationen abgebildet werden.:1. Motivation
2. Stand von Wissenschaft und Technik
2.1. Kondensation in geschichteter Strömung
2.2. Geometrie von Freistrahlen
2.3. Kondensation am Freistrahl
2.4. Blasenmitriss
2.5. Blasenmitriss bei gleichzeitiger Kondensation
2.6. Modellierung
2.7. Anwendung der Erkenntnisse auf den Hypothetischen Störfall
3. Versuchsanlage
3.1. Messtechnik
3.1.1. Schnelle Temperaturmesstechnik
3.1.2. Hochgeschwindigkeitskamera
3.1.3. Infrarotkamera
3.1.4. Temperatur- und Druckmesslanzen
3.2. Abgeleitete Größen
3.3. Messung der Kondensationsrate
3.4. Geschwindigkeits- und Turbulenzmessung
4. Experimente und Ergebnisse
4.1. Geschichtete Strömung
4.2. Freistrahl
4.3. Gasmitriss
5. Zusammenfassung und Ausblick / Reliable predictions on the behaviour of accident scenarios in reactor systems are possible with CFD models if they have been developed and validated on the basis of experiments. Motivated by the processes that occur in a Pressurized Thermal Shock scenario in the primary circuit of a Pressurized Water Reactor, experiments on the Direct Contact Condensation of steam on subcooled water were investigated at high pressures.
The described experimental setup allows to study all three phenomena: stratified flow, jet and bubble entrainment. Comprehensive instrumentation made it possible to gather a considerable amount of information from the experiments. Various imaging techniques allow a particular insight in the flow without feedback into the fluid. Some of the measurement and evaluation methods were specifically developed for the investigation and have been described.
Especially the measurement results of the jet experiments with condensation are comprehensive and unique. The strong turbulence inside the examined jets results in the highest condensation rates in these experiments. Here, the jet diameter profiles were compared for different boundary conditions in order to show that condensation in jets is strongly influenced by ambient pressure.
The gas entrainment experiments are the first documented experiments of their kind. They show that the entrained gas condenses immediately at the point of entrainment with inlet subcooling above 10 K. There is no formation of bubbles or entrainment downwards. Only a negative meniscus is visible, which has a geometry dependent on the boundary conditions. The lower the inlet subcooling and the higher the jet velocity, the deeper the gas meniscus penetrates into the water layer. The amount of entrained gas is small in comparison to the amount of condensation at the jet even at high velocities.
The experiments were essentially designed to provide data for comparison with CFD simulations. In particular, the influence of the ambient pressure on the beam geometry and the condensation rate should be further investigated and reproduced in simulations.:1. Motivation
2. Stand von Wissenschaft und Technik
2.1. Kondensation in geschichteter Strömung
2.2. Geometrie von Freistrahlen
2.3. Kondensation am Freistrahl
2.4. Blasenmitriss
2.5. Blasenmitriss bei gleichzeitiger Kondensation
2.6. Modellierung
2.7. Anwendung der Erkenntnisse auf den Hypothetischen Störfall
3. Versuchsanlage
3.1. Messtechnik
3.1.1. Schnelle Temperaturmesstechnik
3.1.2. Hochgeschwindigkeitskamera
3.1.3. Infrarotkamera
3.1.4. Temperatur- und Druckmesslanzen
3.2. Abgeleitete Größen
3.3. Messung der Kondensationsrate
3.4. Geschwindigkeits- und Turbulenzmessung
4. Experimente und Ergebnisse
4.1. Geschichtete Strömung
4.2. Freistrahl
4.3. Gasmitriss
5. Zusammenfassung und Ausblick
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Dynamics of the free surface of stratified two-phase flows in channels with rectangular cross-sectionsVallée, Christophe 24 April 2012 (has links)
Stratified two-phase flows were investigated at different test facilities with horizontal test sections in order to provide an experimental database for the development and validation of computational fluid dynamics (CFD) codes. These channels were designed with rectangular cross-sections to enable optimal observation conditions for the application of optical measurement techniques. Consequently, the local flow structure was visualised with a high-speed video camera, delivering data with high-resolution in space and time as needed for CFD code validation.
Generic investigations were performed at atmospheric pressure and room temperature in two air/water channels made of acrylic glass. Divers preliminary experiments were conducted with various measuring systems in a test section mounted between two separators. The second test facility, the Horizontal Air/Water Channel (HAWAC), is dedicated to co-current flow investigations. The hydraulic jump as the quasi-stationary discontinuous transition between super- and subcritical flow was studied in this closed channel. Moreover, the instable wave growth leading to slug flow was investigated from the test section inlet. For quantitative analysis of the optical measurements, an algorithm was developed to recognise the stratified interface in the camera frames, allowing statistical treatments for comparison with CFD calculation results.
The third test apparatus was installed in the pressure chamber of the TOPFLOW test facility in order to be operated at reactor typical conditions under pressure equilibrium with the vessel atmosphere. The test section representing a flat model of the hot leg of the German Konvoi pressurised water reactor (PWR) scaled at 1:3 is equipped with large glass side walls in the region of the elbow and of the steam generator inlet chamber to allow visual observations. The experiments were conducted with air and water at room temperature and maximum pressures of 3 bar as well as with steam and water at boundary conditions of up to 50 bar and 264°C. Four types of experiments were performed, including generic test cases as well as transient validation cases of typical nuclear reactor safety issues. As an example, the co-current flow experiments simulate the two-phase natural circulation in the primary circuit of a PWR. The probability distribution of the water level measured in the reactor pressure vessel simulator was used to characterise the flow in the hot leg. Moreover, the flooding behaviour in this conduit was investigated with dedicated counter-current flow limitation experiments. A comparison of the flooding characteristics with similar experimental data and correlations available in the literature shows that the channel height is the characteristic length to be used in the Wallis parameter for channels with rectangular cross-sections. Furthermore, for the analysis of steam/water experiments, condensation effects had to be taken into account. Finally, the experimental results confirm that the Wallis similarity is appropriate to scale flooding in the hot leg of a PWR over a large range of pressure and temperature conditions.
Not least, different examples of comparison between experiment and simulation demonstrate the possibilities offered by the data to support the development and validation of CFD codes. Besides the comparison of qualitative aspects, it is shown exemplarily how to treat the CFD results in order to enable quantitative comparisons with the experiments.
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