Orientador: Elaine Maria Cardoso / Resumo: Nas últimas décadas surgiu a necessidade de dissipar maiores quantidades de energiatérmica, fato que acarretou no aumento do número de estudos em ebulição nucleada e convectivacom o objetivo de produzir trocadores de calor cada vez mais eficientes e compactos. Abusca de produtos cada vez mais eficientes e compactos e a procura de novas técnicas paramelhorar a transferência de calor, garantindo a integridade física do equipamento, continuamcrescendo e a tendência é que continuará assim nos próximos anos. Uma das técnicas que estásendo amplamente pesquisada na comunidade cientifica é o uso de nanofluidos. Os nanofluidosforam desenvolvidos com o intuito de melhorar a condutividade e a difusividade térmicaem relação aos fluidos tradicionais. Muitos experimentos com nanofluidos têm sido desenvolvidosnos últimos anos, mas ainda existem muitas divergências a respeito do efeito dessesfluidos sobre o fenômeno de ebulição. Dentro deste contexto, o presente trabalho tem comoobjetivo a análise teórico-experimental do efeito de superfícies nanoestruturadas e da concentraçãodo nanofluido, a ser depositado sobre a superfície aquecedora, sobre o coeficiente detransferência de calor em regime de ebulição nucleada. Para tanto, testes foram realizadospara fluxos de calor que correspondem ao regime de ebulição nucleada da água deionizada, àtemperatura de saturação (Tsat = 99 °C) e à pressão atmosférica (patm = 98 kPa), sobre superfíciesaquecedoras de cobre com dif... (Resumo completo, clicar acesso eletrônico abaixo) / Abstract: In the last decade, the necessity to dissipate large quantities of heat energy increased,thus leading to an increase on the number of studies in nucleate pool boiling and flow boilingwith the aim of producing more compact and efficient heat exchangers. The search for increasinglyefficient and compact products and for new techniques to improve the heat transfer,ensuring the physical integrity of the equipment, keep growing and it will remain so in thenext years. One of the techniques being widely researched in the scientific community is theuse of nanofluids. The nanofluids have been developed in order to improve the thermal conductivityand diffusivity compared to traditional fluids. Although many experiments withnanofluids have been developed in recent years, there are still many differences related to theeffects of these fluids on the pool boiling phenomenon. In this context, this work aims to analyzethe effects of nanostructured surfaces and different nanofluid concentrations, which aredeposited on the heating surface, on the heat transfer coefficient during the nucleate boilingregime. Therefore, tests were performed to heat fluxes values corresponding to the nucleateboiling regime for deionized water, at saturation temperature (Tsat = 99 °C) and atmosphericpressure (patm = 98 kPa), on copper heating surfaces with different roughness values. Thenanostructured surfaces were produced by maghemite nanoparticle deposition, which isachieved by boi... (Complete abstract click electronic access below) / Mestre

O presente estudo envolve a análise teórico-experimental da transferência de calor através do mecanismo de ebulição em um único tubo e em banco com três tubos horizontais. A análise da literatura permitiu levantar os parâmetros que podem influenciar o coeficiente de transferência de calor na ebulição em banco de tubos e algumas correlações. O aparato experimental foi adaptado para realização de ensaios envolvendo refrigerantes halogenados, 3 tubos dispostos em fileiras paralelas e 3 distintos diâmetros. Nos experimentos foram utilizados os refrigerantes R-11, R-123 (baixa pressão) e R-134a (média pressão), tubos de latão aquecidos internamente com resistências elétricas, com fluxo de calor específico variando entre 1 e 40 kW/'M POT.2'. Através dos resultados foram observados alguns comportamentos inéditos na influência do acabamento superficial e em banco de tubos. Com base no banco de dados levantado, foi desenvolvida uma correlação para o coeficiente de transferência de calor em ebulição em banco de tubos. Os resultados obtidos por esta correlação apresentaram reduzidos desvios em relação aos experimentais. / The research reported herein is a theoretical and experimental investigation of nucleate boiling heat transfer in an isolated tube and a row of three horizontal tubes. The literature review provided enough information to raise the intervening physical parameters and several correlations. The experimental bench has been developed and adapted to perform experiments with several refrigerants, three different tube diameters, and to accommodate a row of three parallel tubes. The experiments have been carried out with refrigerants R-11, R-123 and R-134a. Heating of the brass tubes has been provided by tubular electrical heaters inserted inside the tubes. The heat flux varied from 1 to 40 kW/'M POT.2'. Experiments have been carried out by successively heating two and three tubes. Effects of boiling in tubes underneath (lower level) have been investigated. Finally a correlation for the heat transfer coefficient in successive tubes of a tube bank has been developed. The correlation presents good accuracy with respect to data from the present investigation.

京都大学 / 0048 / 新制・課程博士 / 博士(工学) / 甲第22894号 / 工博第4791号 / 新制||工||1749(附属図書館) / 京都大学大学院工学研究科原子核工学専攻 / (主査)教授 横峯 健彦, 教授 佐々木 隆之, 講師 河原 全作 / 学位規則第4条第1項該当 / Doctor of Philosophy (Engineering) / Kyoto University / DGAM

In nuclear power plants, during operation at high temperatures, there can occur a steam build-up around the fuel rods at an increasing rate. This inhibits the water’s effectivity in removing heat from the rods. When this occurs and reaches a critical point, the temperature in the fuel rods surges, which can lead to them being damaged. This is called critical heat flux (CHF). During operation, the reactor always keeps a safety margin to the point where CHF can occur. The margin to CHF is one of the factors that limits the nuclear power plant’s ability to produce electricity. With the help of the tests that Westinghouse runs, the safety margin to the CHF can be more accurately determined, so that the reactor can safely be closer to the critical point.Westinghouse uses rods that are heated with electricity instead of nuclear fuel. In Westinghouse’s test facility, a problem has been identified, where the uppermost part of the rod has a risk of breaking due to the high temperatures. The temperatures are so high due to the rod being unable to conduct the large amount of current (max. 300kW) through the grid plate, situated at the top. The rod has a tapered end and is hammered into the grid plate’s tapered holes during assembly. The rod’s end is hollow and is attached from above using screws.To find a solution, two theoretical concepts have been developed and an eventual change of rod material has been evaluated. The purpose of the concepts is to limit the risk of problems occurring due to heat increase during operation. Both concepts have reduced hole size and length, to avoid hollow areas around the warmest part of the construction. For concept evaluation, Pugh’s concept selection method has been used. The most appropriate concept has been evaluated to be a reduced hole width, and a deeper hole with a thread insert.

No description available.

A high pressure pool boiling experiment of pressurized R134a is designed and built, utilizing thermochromatic liquid crystal techniques. Liquid crystals thermo-chromatography uses encapsulated liquid crystals that are sensitive to temperature. When exposed to hot temperatures the crystal reflect a blue/violet color, and when exposed to cooler temperatures it reflects a red/orange color. The color value or hue is proportional to its temperature. Using this technique this experiment is capable of studying the physics and thermodynamics of refrigerants under nucleate pool boiling. The main objective of this experiment was the design of the experimental setup. Various designs were tested and validated, of which all incorporated a pressure resistant chamber constructed out of aluminum and glass viewing ports. Design parameters such as the heating element thickness were verified using a transient FEA thermal model. This model, which was developed in ANSYS, verified that this design would be able to capture the thermal response of the thermochromatic liquid crystals. This analysis concluded that a negligible error of 0.02°C is expected due to transient effects. Difficulties were encountered during early stages of development; most notable were imaging limitations such as low camera frame-rates and poor resolution. Since a TLC technique was used to measure the temperature of the boiling surface, a camera system fast enough to capture the thermal response was needed. At bubble frequencies of 30 nucleations per second, it was necessary for the camera to have much higher frame rates. Through the use of two synchronized cameras, the surface temperature, position, size and shape of the bubbles were recorded simultaneously. Two camera systems were designed and tested. The first system consisted of a high speed CMOS camera capable of capturing 1,000 frames per second, and an RBG CCD color camera capable of 30 Frames per second. However, this system was limited the slow frame rate and low resolution of the RBG camera. The second system used two high resolution and fast shutter speed cameras, which were able to capture fast bubble nucleations. This method required the assumption that under constant operating conditions, the path of one bubble was identical to the next. This method was tested utilizing the high speed camera, and was shown that there was less than a .04% deviation from the path any bubble to that of the next. Detailed analysis of nucleating surface temperatures using thermochromatic liquid crystal technique and temporal-temperature response under various heat flux and at 813.6kPa (118Psia) and 882.5kPa (128Psia) was performed. It is seen that temperature distribution is quite varied in each case. At high pressures the size of nucleation site decreases, giving rise to an increase in the surface temperature. Bubble growth is also analyzed through the use of high speed cameras and compared to temperature distributions. Simultaneous temperature and bubble size measurements provided a correlation between bubble growth and heat transfer. Boiling parameters such as bubble frequency, bubble size, and contact area are also analyzed. From the surface temperature plots, the local and average heat transfer coefficients were calculated as a function of time and bubble dynamics.

A pool boiling experimental facility has been designed and built to investigate nucleate pool boiling in water under sub atmospheric pressure. Liquid crystal thermography, a non intrusive technique, is used for the determination of surface temperature distributions. This technique uses encapsulated liquid crystals that reflect definite colors at specific temperatures and viewing angle. Design of the test section is important in this experimental study. Since a new TLC is required for every new set of test conditions, a permanently sealed test section is not an option. The real challenge is to design a leak proof test section which is flexible so that it can be taken apart easily. A plexiglass test section, including a top chamber with an internal volume of 60.9 x 60.9 x 66.4 mm and a bottom plate of 5.5mm thickness is designed and assembled together using quick grips. In the test section, water is boiled using 85.0mm x 16.0mm and 0.050mm thick Fecralloy® as the heating element. The TLC sheet is attached to the bottom plate and the heating element is placed on top of TLC so that the temperature distribution of the heating element during boiling can be interpreted from TLC. A camera system fast enough to capture the thermal response of the TLC and an arrangement to capture both hue of the TLC and growth of the bubble on the same frame has been designed and successfully used. This system allowed recording of position, size and shape of the bubble with synchronized surface temperature. In order to get hue vs. temperature relation, in-situ calibration of the TLC is performed for each test condition with the present experimental setup and lighting conditions. It is found that the calibration curve of the TLC at atmospheric pressure is different from the calibration curve of the same TLC at subatmospheric pressures. The maximum temperature difference between the two curves for the same hue is found to be only 0.6°C. The experiment is run at four different test conditions of subatmospheric pressure and low heat flux. It is run at system pressures of 6.2kPa (0.89Psi) and 8.0kPa (1.16Psi) with a constant heat flux of 1.88kW/m2 and 2.70kW/m2, and a constant heat flux of 2.70kW/m2, 3.662kW/m2 and 4.50 kW/m2 respectively. Analysis of nucleating surface temperatures using thermochromic liquid crystal technique is performed for these test conditions and the bubble dynamics is studied. The temperature distribution is quite varied in each case and the temperature is at its maximum value at the center of the bubble and it decreases radially from the center. The dry spot observed during the experiments indicates that the process of evaporation of the microlayer is dominant at subatmospheric pressures. It is observed that at very low pressure and heat flux the bubble growth is accompanied by the neck formation. Boiling parameters such as bubble frequency, bubble size and contact are also analyzed and a summary of these results for four different test conditions is presented and the relevant differences between the cases are discussed and the effect of increase in pressure and heat flux is noted.

Study of quench cooling is very important in nuclear reactor safety for limiting the extent of core damage during the early stages of severe accidents after Loss of Coolant Accidents (LOCA). Quench of a hot dry surface involves the rapid decrease in surface temperature resulting from bringing the hot surface into sudden contact with a coolant at a lower temperature. The quench temperature is the onset of the rapid decrease in the surface temperature and corresponds to the onset of destabilization of a vapor film that exists between the hot surface and the coolant. Re-wetting the surface is the establishment of direct contact between the surface and the liquid at the so-called re-wetting temperature. Re-wetting is characterized by the formation of a wet patch on the surface which then spreads to cover the entire surface. Situations involving quench and re-wetting heat transfer are encountered in a number of postulated accidents in Canada Deuterium Uranium (CANDU) reactors, such as re-wetting of a hot dry calandria tube in a critical break LOCA. This accident results in high heat transfer from the calandria tube to the surrounding moderator liquid which can cause the calandria tube surface to experience dryout and a subsequent escalation in the surface temperature. If the calandria tube temperature is not reduced by initiation of quench heat transfer, then this may lead to subsequent fuel channel failure. In literature very limited knowledge is available on quench and re-wetting of hot curved surfaces like the calandria tubes. In this study, a Water Quench Facility (WQF) has been constructed and a series of experiments were conducted to investigate the quench and re-wetting of hot horizontal tubes by a vertical rectangular water multi-jet system. The tubes were heated to a temperature between 380-800°C in a controlled temperature furnace then cooled to the jet temperature. The temperature variation with time in the circumferential and the axial directions of the tubes has been measured. The twophase flow behavior and the propagation of the re-wetting front around and along the tubes were simultaneously observed by using a high-speed camera. The effects of several parameters on the cooling process have been investigated. These parameters include: initial surface temperature, water subcooling (in the range 15- 800C), jet velocity (in the range 0.15-1.60 m/s), tube solid material (brass, steel and Alumina), surface curvature, tube wall thickness, jet orientation and number of jets. The variables studied include the re-wetting delay time (time to quench after initiating the cooling process), there-wetting front propagation velocity, the quench and re-wetting temperatures, the quench cooling rates and the boiling region size. The quench and the re-wetting temperatures as well as the re-wetting delay time were found to be a strong function of water subcooling. The quench and re-wetting temperatures increase with increasing water subcooling. The rewetting delay time decreases with increasing the water subcooling, decreasing initial surface temperature, increasing liquid velocity and decreasing the surface curvature. There-wetting front velocity is mainly dependent on the initial surface temperature and water subcooling. The re-wetting velocity increases by decreasing the initial surface temperature and by increasing the water subcooling. Decreasing the surface curvature was found to also increase the re-wetting front velocity. Correlations of the phenomena studied have been developed and provided good prediction of the experimental data collected in this study and data available from literature. The. results of this study provide novel knowledge and an experimental database for mechanistic modeling of quench heat transfer on calandria tube surfaces that experience dryout and film boiling. / Thesis / Doctor of Philosophy (PhD)

<div>Nucleate boiling is an efficient heat transfer mechanism that enables the dissipation of high heat fluxes at low temperature differences. Heat transfer phenomena during nucleate boiling are closely linked to the two-phase flow morphology that evolves in time and based on the operating conditions. In particular, the critical heat flux, which is the upper limit for the nucleate boiling regime, can be triggered by hydrodynamic mechanisms resulting from interactions between the liquid and vapor phases. The aim of this thesis is to characterize the two-phase flow morphology evolution during nucleate boiling at high heat fluxes in two configurations: pool boiling, and confined and submerged two-phase jet impingement. The characterization is performed via non-invasive, high-speed optical based diagnostic tools. </div><div>Experimental characterization of liquid-vapor interfaces during boiling is often challenging because the rapidly evolving vapor structures are sensitive to invasive probes and multiple interfaces can occlude one another along a line of sight. In this thesis, a liquid-vapor interface reconstruction technique based on high-speed stereo imaging is developed. Images are filtered for feature enhancement and template matching is used for determining the correspondence of local features of the liquid-vapor interfaces between the two camera views. A sampling grid is overlaid on the reference image and windows centered at each sampled pixel are compared with windows centered along the epipolar line in the target image to obtain a correlation signal. To enhance the signatures of true matches, the correlation signals for each sampled pixel are averaged over a short time ensemble correlation. The three-dimensional coordinates of each matched pixel are determined via triangulation, which yields a set of points in the physical world representing the liquid-vapor interface. The developed liquid-vapor interface reconstruction technique is a high-speed, flexible and non-invasive alternative to the various existing methods for phase-distribution mapping. This technique also has the potential to be combined with other optical-based diagnostic tools, such as tomographic particle image velocimetry, to further understand the phase interactions.<br></div><div>The liquid-vapor interface reconstruction technique is used to characterize liquid-vapor interfaces above the heated surface during nucleate pool boiling, where the textured interface resulting from the boiling phenomena and flow interactions near the heated surface is particularly suited for reconstruction. Application of the reconstruction technique to pool boiling at high heat fluxes produces a unique quantitative characterization of the liquid-vapor interface morphology near heated surface. Analysis of temporal signals extracted from reconstructions indicate a clear transition in the nature of the vapor flow dynamics from a plume-like vapor flow to a release mode dominated by vapor burst events. Further investigation of the vapor burst events allows identification of a characteristic morphology of the vapor structures that form above the surface that is associated to the square shape of the heat source. Vapor flow morphology characterization during pool boiling at high heat fluxes can be used to inform vapor removal strategies that delay the occurrence of the critical heat flux during pool boiling.</div><div>As compared to pool boiling, nucleate boiling can be sustained up to significantly higher heat fluxes during two-phase jet impingement. The increases in critical heat flux are explained via hydrodynamic mechanisms that have been debated in the literature. The connection between two-phase flow morphology and the extension of nucleate boiling regime is investigated for a single subcooled jet of water that impinges on a circular heat source via high-speed visualization from two synchronized top and side views of the confinement gap. When boiling occurs under subcooled exit flow conditions and at moderate heat fluxes, the regular formation and collapse of vapor structures that bridge the heated surface and the orifice plate is observed, which causes significant oscillations in the pressure drop across. Under saturated exit flow conditions, the vapor agglomerates in the confinement gap into a bowl-like vapor structure that recurrently shrinks, due to vapor break-off at the edge of the orifice plate, and replenishes due to vapor generation. The optical visualizations from the top of the confinement gap provide a unique perspective and indicate that the liquid jet flows downwards through the vapor structure, impinges on the heated surface, and then flows underneath the vapor structure, as a fluid wall jet the keeps the heated surface wetted such that discrete bubbles continue to nucleate. At high heat fluxes, intense vapor generation causes the fluid wall jet to transition from a bubbly to a churn-like regime, and some liquid droplets are sheared off into the vapor structure. The origin of critical heat flux appears to result from a significant portion of the liquid in the wall jet being deflected off the surface, and the remaining liquid film on the surface drying out before reaching the edge of the heater.</div><div>The flow morphology characterizations presented in this dissertation further the understanding of flow and heat transfer phenomena during nucleate boiling. In the pool boiling configuration, the vapor release process was quantitatively described; during two-phase jet impingement, a possible mechanism for critical heat flux was identified. Opportunities for future work include the utilization of image processing techniques to extract quantitative measurements from two-phase jet impingement visualizations. Also, the developed liquid-vapor interface reconstruction technique can be applied to a boiling situation with a simpler liquid-vapor interface geometry, such as film boiling, to generate benchmark data for validation and development of numerical models.</div><div><br></div>

O estudo presente constitui uma análise da influência do acabamento superficial no coeficiente de transferência de calor na ebulição nucleada de refrigerantes halogenados. Dados para três superfícies distintas (cobre, latão e aço inoxidável), dois fluidos refrigerantes (R123 e R134a) e pressões reduzidas entre 0,023 e 0,26 são analisados com o intuito de verificar a influência da rugosidade nestes três parâmetros. O efeito da rugosidade foi avaliado com três acabamentos distintos (massa polidora, lixa e jato de areia) cobrindo uma faixa de rugosidades médias variando desde 0,03 até 10,5 micrômetro. Uma análise de diversas publicações da literatura foi levada a cabo, tendo sido particularmente investigadas algumas correlações que consideram o efeito do acabamento superficial em sua estimativa do coeficiente de transferência de calor. As tendências destas correlações são comparadas entre si e com os dados experimentais. A análise dos resultados permitiu levantar tendências inéditas na literatura consultada. A superfície em ebulição recebeu especial atenção com a obtenção de microfotografias e o cálculo de diversos parâmetros de rugosidade. Foram, ainda, investigados efeitos de envelhecimento da superfície, caracterizado pela diminuição do coeficiente de transferência de calor ao longo do tempo de ebulição. / The present research has been focused in an analysis of the effect of surface finishing on nucleate boiling heat transfer coefficient of halocarbon refrigerants. Experimental data for three different surface material (cooper, brass and stainless steel), two refrigerants (R123 and R134a) and reduced pressures between 0.023 and 0.26 have been analyzed aiming to verify the roughness effects on these three parameters. Three different finishing processes (polishing, emery papering and shot pining) have been used to result in an average roughness range from 0.03 to 10.5 micrometer. An analysis of varied publications and some correlations, particularly those which estimate the effect of surface roughness in heat transfer coefficient, has been done. The tendencies from these correlations have been compared with themselves and with experimental data. These results have shown some effects still unpublished. The boiling surface has received an especial attention, micro-photography has been taken and various parameters have been evaluated. Ageing effects, characterized by the reduction of heat transfer coefficient, have been verified and analyzed.