Готові списки джерел за темами / Bundle of tubes

Добірка наукової літератури з теми "Bundle of tubes"

Автор: Grafiati

Опубліковано: 7 липня 2024

Оновлено: 7 липня 2024

Оформте джерело за APA, MLA, Chicago, Harvard та іншими стилями

Оберіть тип джерела:

Ознайомтеся зі списками актуальних статей, книг, дисертацій, тез та інших наукових джерел на тему "Bundle of tubes".

Біля кожної праці в переліку літератури доступна кнопка «Додати до бібліографії». Скористайтеся нею – і ми автоматично оформимо бібліографічне посилання на обрану працю в потрібному вам стилі цитування: APA, MLA, «Гарвард», «Чикаго», «Ванкувер» тощо.

Також ви можете завантажити повний текст наукової публікації у форматі «.pdf» та прочитати онлайн анотацію до роботи, якщо відповідні параметри наявні в метаданих.

Статті в журналах з теми "Bundle of tubes":

Chan, A. M. C., and M. Shoukri. "Boiling Characteristics of Small Multitube Bundles." Journal of Heat Transfer 109, no. 3 (August 1, 1987): 753–60. http://dx.doi.org/10.1115/1.3248154.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Boiling characteristics of multitube bundles have been investigated experimentally. Small bundles of up to nine rows were used. Void fraction profiles in the test vessel, tube surface temperatures, power input to individual tubes, and critical heat fluxes were measured for different bundle arrangements and boiling conditions. The data were used to study the system hydrodynamics, bundle heat transfer coefficients, and bundle critical heat flux. The data showed that for lower heat fluxes, the heat transfer characteristics are affected by the system hydrodynamics resulting in higher heat transfer coefficients, whereas at higher heat fluxes nucleate boiling is the dominant mechanism. The data also showed that within a tube bundle, the vapor rising from lower tubes enhances the CHF characteristics of the upper tubes.

Deeb, Rawad. "Flow and heat transfer characteristics of staggered mixed circular and drop-shaped tube bundle." Physics of Fluids 34, no. 6 (June 2022): 065126. http://dx.doi.org/10.1063/5.0090732.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

The purpose of this study is to clarify heat transfer and fluid flow behavior across six-row mixed tube bundles. The tube bundle consists of circular and drop-shaped cross sections in a staggered arrangement. The Reynolds number Re for the flow is varied from 1.78 × 103 to 18.72 × 103. Six cases of the mixed tube bundle were considered. The results of the mixed tube bundles were compared with those of the circular (case I) and drop-shaped ones (case II). The Ansys Fluent software package was utilized to predict the flow pattern over the tube bundles. The results of the numerical simulation showed that the cross-sectional shape of the tubes and their location in the bundle significantly affect the heat transfer and pressure drop in the bundle. Case IV (circular tubes in the first, third, and fifth rows and drop-shaped tubes in the second, fourth, and sixth rows) increases the average Nusselt number [Formula: see text] by about 1.11%–8.10% and 47.86%–49.04% compared to that of the circular and drop-shaped tube bundles, respectively. Case VII (drop-shaped tubes in the first, second, fourth, and sixth rows and circular tubes in the third and fourth rows) has the lowest friction factor [Formula: see text] compared to the other cases of circular and mixed tube bundles. Moreover, the maximum values of the thermal–hydraulic performance [Formula: see text] were achieved for case IV at Re = 1.78 × 103 and the case VII at Re >1.78 × 103, which were about 14.55% and (2.08–4.49)%, respectively, higher than those obtained for the drop-shaped tube bundle. Generalized correlations of [Formula: see text], [Formula: see text], and [Formula: see text] for the studied mixed tube bundles were predicted.

Honda, H., B. Uchima, S. Nozu, H. Nakata, and E. Torigoe. "Film Condensation of R-113 on In-Line Bundles of Horizontal Finned Tubes." Journal of Heat Transfer 113, no. 2 (May 1, 1991): 479–86. http://dx.doi.org/10.1115/1.2910586.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Film condensation of R-113 on in-line bundles of horizontal finned tubes with vertical vapor downflow was experimentally investigated. Two tubes with flat-sided annular fins and four tubes with three-dimensional fins were tested. The test sections were 3×15 tube bundles with and without two rows of inundation tubes at the top. Heat transfer measurements were carried out on a row-by-row basis. The heat transfer enhancement due to vapor shear was much less for a finned tube bundle than for a smooth tube bundle. The decrease in heat transfer due to condensate inundation was more marked for a three-dimensional fin tube than for a flat-sided fin tube. The predictions of the previous theoretical model for a bundle of flat-sided fin tubes agreed well with the measured data for low vapor velocity and a small to medium condensate inundation rate. Among the six tubes tested, the highest heat transfer performance was provided by the flat-sided fin tube with fin dimensions close to the theoretically determined optimum values.

Deeb, Rawad. "Effect of angle of attack on heat transfer and hydrodynamic characteristics for staggered drop-shaped tubes bundle in cross-flow." Proceedings of the Russian higher school Academy of sciences, no. 3 (December 18, 2020): 21–36. http://dx.doi.org/10.17212/1727-2769-2020-3-21-36.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Tube bundles can be used as a separation heat exchanger in the organic Rankine cycle power plants (ORC), while the hot gas passes over the outer surface, and the working substance ORC flows inside the tubes. A numerical study has been conducted to clarify heat transfer and hydrodynamics of a cross-flow heat exchanger with staggered drop-shaped tubes at different flow angles of attack in comparison with circular tubes of the same equivalent diameter. The study was performed for the Reynolds number Re= 1.8  103 ~ 9.4  103, the longitudinal and transverse spacing of the tubes in the bundle are the same and are equal to 37 mm. Four cases of the tube’s arrangement with different angles of attack were investigated: 0, 45, 135, and 180 angles. The article presents a literature review related to the subject of the study. A mathematical and numerical model has been developed to calculate the heat transfer coefficient of the studied staggered drop-shaped tubes bundle using the ANSYS package, taking into account the stress-strain state of the tubes. Correlations of the average Nusselt numbers and the friction coefficient for the considered bundles in terms of the Reynolds number and angle of attack were presented. The results reveal that the thermal–hydraulic performance of the drop-shaped tubes bundle with zero-angle of attack is about 1.6 ~ 1.7 times greater than the circular one.

Ai, Shiqin, Chao Sun, Yuechan Liu, and Yuelin Li. "Numerical Simulation of Flow-Induced Vibration of Three-Dimensional Elastic Heat Exchanger Tube Bundle Based on Fluid-Structure Coupling." Shock and Vibration 2022 (January 12, 2022): 1–17. http://dx.doi.org/10.1155/2022/8980562.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

The reliability of the heat exchanger tube bundle not only affects the economic efficiency of production but also relates to the normal development of production safety and health. To study the flow-induced vibration of tube bundles, a three-dimensional finite element model of heat exchange tubes and watersheds inside and outside the tubes was established to explore the flow-induced vibration characteristics of tube bundles and analyze the natural frequencies of single-span and multispan heat exchange tubes. Considering the randomness of the effective support between the tube bundle and the support plate of the heat exchanger, the natural frequency and vibration mode of the four-span tube with failure of the tube bundle support are analyzed. On this basis, the vibration caused by the two-way coupling flow between tube and tube outflow is calculated. Finally, the flow-induced vibration characteristics of the five-tube bundle with two different pitch-diameter ratios are analyzed. The calculation results show that the error between the calculated natural frequencies and the theoretical values is less than 3%, and within the allowable error range, the natural frequencies of the same order decrease with the increase of the number of support failures. The vibration frequencies of single-span and multispan tube bundles are consistent with the lift and drag frequencies, the vibration displacement curves show typical Strouhal modes, and the amplitude increases with the increase of fluid velocity. Vibration displacement curves of symmetrical spans of multispan tube bundles are similar in shape and amplitude. With the increase of tube bundle spacing, the vibration characteristics become more obvious.

Blevins, R. D., and M. M. Bressler. "Acoustic Resonance in Heat Exchanger Tube Bundles—Part I: Physical Nature of the Phenomenon." Journal of Pressure Vessel Technology 109, no. 3 (August 1, 1987): 275–81. http://dx.doi.org/10.1115/1.3264863.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

The intense acoustic resonance resulting from gas flow across a bank of heat exchanger tubes in a duct has been investigated experimentally and theoretically. At low gas velocities, the acoustic tone emanating from tube bundles increases in proportion to the flow velocity. When the frequency approaches a bound acoustic transverse mode of the tube bundle, intense sound can result. Sound levels as high as 173 db were measured within the bundle. During resonance, the sound correlates vortex shedding from the tubes and the pressure drop increases in some bundles.

Wu, Zhiwei, and Caifu Qian. "Study on Behavior of the Heat Exchanger with Conically-Corrugated Tubes and HDD Baffles." ChemEngineering 6, no. 1 (January 2, 2022): 1. http://dx.doi.org/10.3390/chemengineering6010001.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Baffles with holes in different diameters (or HDD baffles) and conically-corrugated tubes are respectively longitudinal flow baffle and high-efficiency heat exchange tubes proposed by the author. In this paper, vibrations of tube bundles with HDD baffles and fluid flow as well as heat transfer inside conically-corrugated tubes were numerically simulated, and the heat exchanger with conically-corrugated tubes and HDD baffles was tested for the heat transfer efficiency. It is found that compared with the traditional segmental baffles, tube bundle vibrations in heat exchangers, if using the HDD baffles, can be significantly reduced. Regarding heat transfer efficiency, conically-corrugated tubes are much better than smooth tubes and even better than other high-efficiency heat transfer tubes. Compared with the traditional heat exchangers, heat exchangers constructed with conically-corrugated tubes and the HDD baffles can provide better heat transfer efficiency and less tube bundle vibration.

Honda, H., B. Uchima, S. Nozu, E. Torigoe, and S. Imai. "Film Condensation of R-113 on Staggered Bundles of Horizontal Finned Tubes." Journal of Heat Transfer 114, no. 2 (May 1, 1992): 442–49. http://dx.doi.org/10.1115/1.2911293.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Film condensation of R-113 on staggered bundles of horizontal finned tubes with vertical vapor downflow was experimentally investigated. Two tubes with flat-sided annular fins and four tubes with three-dimensional fins were tested. The condensate flow and heat transfer characteristics were compared with the previous results for in-line bundles of the same test tubes and a staggered bundle of smooth tubes. The decrease in heat transfer due to condensate inundation was most significant for the in-line bundles of the three-dimensional fin tubes, whereas the decrease was very slow for both the staggered and in-line bundles of the flat-sided fin tubes. The predictions of the previous theoretical model for a bundle of flat-sided fin tubes agreed fairly well with the measured data at a low vapor velocity. The highest heat transfer performance was provided by the staggered bundle of flat-sided fin tubes with fin dimensions close to the theoretically determined optimum values.

Memory, S. B., S. V. Chilman, and P. J. Marto. "Nucleate Pool Boiling of a TURBO-B Bundle in R-113." Journal of Heat Transfer 116, no. 3 (August 1, 1994): 670–78. http://dx.doi.org/10.1115/1.2910921.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Heat transfer measurements were made during nucleate boiling of R-113 from a bundle of 15 electrically heated, copper TURBO-B tubes arranged in an equilateral triangular pitch, designed to simulate a portion of a flooded evaporator. Five of the tubes that were oriented in a vertical array on the centerline of the bundle were each instrumented with six wall thermocouples. For increasing heat flux, the incipient boiling wall superheat of upper tubes decreased as lower tubes were activated. In the boiling region at low heat fluxes (≈ 1 kW/m2), the average bundle heat transfer coefficient was 4.6 times that obtained for a smooth tube bundle (under identical conditions) and 1.6 times greater than that obtained for a single TURBO-B tube; a similar bundle factor has been reported for a smooth tube bundle. At high heat fluxes (100 kW/m2), the average bundle heat transfer coefficient was 3.6 times that of a smooth tube bundle. Furthermore, there was still a significant bundle factor (1.22), contrary to a smooth tube bundle, where all effect of lower tubes was eliminated at high heat fluxes.

Fabrykiewicz, Maciej, and Janusz T. Cieśliński. "Effect of Tube Bundle Arrangement on the Performance of PCM Heat Storage Units." Energies 15, no. 24 (December 9, 2022): 9343. http://dx.doi.org/10.3390/en15249343.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

The results of a comprehensive study on the charging and discharging of latent heat storage systems (LHSS) are presented. Multi-tube shell-and-tube units with variable layouts of tube bundles are examined. Two tube arrangements—in-line and staggered—are tested. A variable number of tubes and different tube positions in a bundle are investigated. Moreover, two pitch ratios are studied. Three commercially available substances are used as phase change materials (PCM). The results show that increasing the number of tubes reduces both the charging and discharging times. It is found that for a bundle of seven tubes with a pitch ratio s/d = 4.5, the in-line tube arrangement results in a shorter charging time, but the discharging time is shorter for a staggered tube arrangement.

Більше джерел

Дисертації з теми "Bundle of tubes":

Mazzone, Robert Walter. "Enhanced condensation of R-113 on a small bundle of horizontal tubes." Thesis, Monterey, California. Naval Postgraduate School, 1991. http://hdl.handle.net/10945/43769.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Condensation of r-113 was studied using an evaporator condenser test platform. the condenser section contained four horizontal tubes (nominal outer diameter 15.9 mm)forming a vertical in line column with a pitch-to-diameter ratio of 2.25 and a condensing length of 1.2 m. the condenser tubes could be operated either individually (ie. as a single tube apparatus) or as a small tube bundle. this allowed investigation of the effects of condensate inundation on different types of condenser tubes. tubes tested were smooth copper tubes, copper/nickel korodense roped tubes, korodense tubes wrapped with wire, and copper /nickel finned tubes (26 fpi). the outside heat transfer coefficient was calculated by experimentally determining the overall heat transfer coefficient and then using a modified wilson plot procedure. great care was taken to ensure the results were not vitiated by the presence of non condensibles. results obtained with smooth copper tubes are in agreement with published data and verify satisfactory operation of the test platform. furthermore, problems associated with the apparatus encounted by previous workers were successfully overcome. in comparison to the top smooth tubes, the copper nickel to korodense tube yielded about a 22% increase.

Mabrey, Burlin Davis. "Condensation of refrigerants on small tube bundles." Thesis, Monterey, California. Naval Postgraduate School, 1988. http://hdl.handle.net/10945/22984.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Approved for public release; distribution is unlimited
The construction of an apparatus for the condensation performance testing of a horizontal bundle of four tubes with various refrigerants was completed. The apparatus was instrumented, and data reduction software was developed to provide bundle and single tube condensation data. Two tube bundles were tested, smooth copper tubes and low integral-fin copper-nickel tubes, with two refrigerants, R-114 and R-113. An enhancement ratio of about 2.0 for the overall heat transfer coefficient was demonstrated for the finned tubes over the smooth tubes. Internal contamination, possibly due to a breakdown of the refrigerant molecules when subjected to high temperatures in the boiling chamber, inhibited further meaningful data collection. Recommendations for improvement of the test apparatus are made.
http://archive.org/details/condensationofre00mabr
Lieutenant, United States Navy

Beech, Philip Michael. "Filmwise condensation of high velocity downward flowing steam on a bundle of horizontal tubes." Thesis, Queen Mary, University of London, 1995. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.309675.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Bazin, Clément. "Numerical and experimental studies of two-phase flows interacting with a bundle of tubes." Electronic Thesis or Diss., Institut polytechnique de Paris, 2023. http://www.theses.fr/2023IPPAX106.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Les générateurs de vapeur (GV) des centrales nucléaires sont composés de faisceaux de tubes soumis à des écoulements diphasiques eau-vapeur. Les vibrations liées à cette interaction peuvent induire des dommages (fatigue et usure par frottement et chocs) pouvant entraîner de graves conséquences pour la sûreté nucléaire.Dans le cadre de la prévention des risques vibratoires des tubes de GV des études expérimentales sont réalisées à l'aide de faisceaux analytiques de tubes droits soumis à un écoulement transverse diphasique.En parallèle, il est également important de développer un outil de simulation numérique permettant d'accéder à des données et des informations difficilement mesurables.L'objectif de cette thèse est donc de simuler l’interaction entre un fluide diphasique et une structure rigide (tube unique ou faisceau de tubes), à l'aide du code NEPTUNE_CFD. Ces simulations doivent permettre de reproduire le chargement mécanique exercé par le fluide sur les tubes. La modélisation employée dans cette thèse repose sur un modèle à deux-fluides - trois-champs, comprenant un champ liquide continu, un champ de gaz dispersé, composé de bulles peu déformées, et un champ hybride dispersé-continu pour tenir compte des bulles très déformées et des poches de gaz. La première partie de ce travail s'est concentrée sur la validation du couplage diphasique-turbulence liquide ainsi que sur la modification et l'adaptation de la modélisation pour mieux prendre en compte la présence d'une structure immergée. De nouvelles modélisations pour la force de dispersion turbulente, les termes sources de coalescence et fragmentation, la masse ajoutée et le critère d'activation du champ continu ont été proposées. Dans la deuxième partie de ce travail, nous avons simulé l’écoulement diphasique autour d’un tube unique fixe, afin d'en extraire une physique sous-jacente et d'identifier ses limites et lacunes. Enfin, dans la dernière partie de ce travail, nous avons simulé l’interaction d’un écoulement diphasique avec un faisceau de tubes rigides. Les résultats numériques ont été comparés aux mesures expérimentales. Cette approche nous a permis de justifier l'intérêt de notre modélisation, de trouver des similitudes entre les résultats numériques et expérimentaux, tout en proposant des pistes d'amélioration
The steam generators (SG) in nuclear power plants are made up of bundles of tubes subjected to two-phase water-steam flows. Vibrations related to this interaction can cause damage (fatigue, wear due to friction and shocks) that can lead to serious consequences for nuclear safety.In the context of preventing vibrational risks in SG tubes, experimental studies are conducted using analytical bundles of straight tubes subjected to transverse two-phase flow. In parallel, it is also important to develop a numerical simulation tool to access data and information that are difficult to measure.The goal of this work is to simulate the interaction between a two-phase fluid and a rigid structure (single tube or bundle of tubes) using the NEPTUNE_CFD code. These simulations aim to reproduce the mechanical loading exerted by the fluid on the tubes. The modeling used in this work is based on a two-fluid - three-field model, including a continuous liquid field, a dispersed gas field made up of slightly deformed bubbles, and a dispersed-continuous hybrid field to account for highly deformed bubbles and gas pockets. The first part of this work focused on the validation of the two-phase liquid-turbulence coupling as well as the modification and adaptation of the modeling to better account for the presence of an immersed structure. New models for turbulent dispersion force, source terms of coalescence and break-up, added mass, and the activation criterion of the continuous field were proposed. In the second part of this work, we simulated the two-phase flow around a fixed single tube to extract underlying physics, and identify its limitations and shortcomings. Finally, in the last part of this work, we simulated the interaction of a two-phase flow with a bundle of rigid tubes. The numerical results were compared to experimental measurements. This approach allowed us to justify the relevance of our modeling, find similarities between numerical and experimental results, while also suggesting areas for improvement

Ramadan, Abdulghani. "Numerical And Experimental Investigation Of Forced Filmwise Condensation Over Bundle Of Tubes In The Presence Of Noncondensable Gases." Phd thesis, METU, 2006. http://etd.lib.metu.edu.tr/upload/3/12607831/index.pdf.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

The problem of the forced film condensation heat transfer of pure steam and steam-air mixture flowing downward a tier of horizontal cylinders is investigated numerically and experimentally. Liquid and vapor-air mixture boundary layers were solved by an implicit finite difference scheme. The effects of the free stream non-condensable gas (air) concentration, free stream velocity (Reynolds number), cylinder diameter, temperature difference and angle of inclination on the condensation heat transfer are analyzed. Inline and staggered tubes arrangements are considered. The mathematical model takes into account the effect of staggering of the cylinders and how condensation is affected at the lower cylinders when condensate does not fall on to the center line of the cylinders. An experimental setup was also manufactured and mounted at METU workshop. A set of experiments were conducted to observe the condensation heat transfer phenomenon and to verify the theoretical results. Condensation heat transfer results are available in ranges from (U&
#61605
= 1 - 30 m/s) for free stream velocity, (m1,&
#61605
= 0.01 -0.8) for free stream air mass fraction, (d = 12.7 -50.8 mm) for cylinder diameter and (T&
#61605
-Tw =10-40 K) for temperature difference. Results show that
a remarked reduction in the vapor side heat transfer coefficient is noticed when very small amounts of air mass fractions present in the vapor. In addition, it decreases by increasing in the cylinder diameter and the temperature difference. On the other hand, it increases by increasing the free stream velocity (Reynolds number). Average heat transfer coefficient at the middle and the bottom cylinders increases by increasing the angle of inclination, whereas, no significant change is observed for that of the upper cylinder. Although some discrepancies are noticed, the present study results are inline and in a reasonable agreement with the theory and experiment in the literature. Down the bank, a rapid decrease in the vapor side heat transfer coefficient is noticed. It may be resulted from the combined effects of inundation, decrease in the vapor velocity and increase in the non-condensable gas (air) at the bottom cylinders in the bank. Differences between the present study results and the theoretical and the experimental data may be resulted from the errors in the numerical schemes used. These errors include truncation and round off errors, approximations in the numerical differentiation for interfacial fluxes at the vapor-liquid interface, constant properties assumption and approximations in the initial profiles. Mixing and re-circulation in the steam-air mixture at the lower tubes may be the other reasons for these deviations.

Marcel, Thibaud. "Simulation numérique et modélisation de la turbulence statistique et hybride dans un écoulement de faisceau de tubes à nombre de Reynolds élevé dans le contexte de l'interaction fluide-structure." Thesis, Toulouse, INPT, 2011. http://www.theses.fr/2011INPT0109/document.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

La prédiction des instabilités fluide-élastique qui se développent dans un faisceau de tubes est importante pour la conception des générateurs de vapeur dans les centrales nucléaires, afin de prévenir les accidents liés à ces instabilités. En effet, ces instabilités fluide-élastique, ou flottements, conduisent à une fatigue vibratoire des matériaux, voire à des chocs entre les tubes, et par la suite, à des dégâts importants. Ces aspects sont d'une grande complexité pour les applications scientifiques impliquant l'industrie nucléaire. Le présent travail est issu d'une collaboration entre l'EDF, le CEA et l'IMFT. Elle vise à améliorer la simulation numérique de cette interaction fluide- structure dans le faisceau de tubes, en particulier dans la gamme de paramètres critiques favorisant l'apparition d'un amortissement négatif du système et de l'instabilité fluide-élastique
The prediction of fluid-elastic instabilities that develop in a tube bundle is of major importance for the design of modern heat exchangers in nuclear reactors, to prevent accidents associated with such instabilities. The fluid-elastic instabilities, or flutter, cause material fatigue, shocks between beams and damage to the solid walls. These issues are very complex for scientific applications involving the nuclear industry. This work is a collaboration between EDF, CEA and IMFT. It aims to improve the numerical simulation of the fluid-structure interaction in the tube bundle, in particular in the range of critical parameters contribute to the onset of damping negative system and the fluid-elastic instability

Belghazi, Mourad. "Condensation d'un fluide pur et de mélanges zéotropes à l'extérieur d'un faisceau de tubes à surface améliorée." Université Joseph Fourier (Grenoble), 2001. http://www.theses.fr/2001GRE10055.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Blanc, Philippe. "Condensation des fluides frigorigènes HFC134a et HFC22 à l'extérieur d'un faisceau de tubes horizontaux améliorés." Université Joseph Fourier (Grenoble ; 1971-2015), 1994. http://www.theses.fr/1994GRE10221.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

L'utilisation de nouveaux fluides frigorigenes respectueux de notre environnement remet en cause les connaissances etablies pour le dimensionnement des installations frigorifiques et de conditionnement d'air. Les condenseurs de type tema x, largement utilises dans de telles applications, sont composes d'un faisceau de tubes horizontaux ameliores a l'exterieur desquels vient se condenser la vapeur de fluide frigorigene. Le dimensionnement optimal d'un tel echangeur necessite la prise en compte de l'effet d'inondation du condensat le long des rangees de tubes du faisceau. L'approche experimentale reste dans ce domaine un moyen privilegie d'amelioration des connaissances. L'experimentation est realisee sur une maquette simulant une partie du condenseur. Les mesures locales effectuees pour deux fluides frigorigenes et deux geometries de tubes ameliores ont permis d'etablir un nombre important de donnees experimentales. Leur confrontation avec divers modeles de la litterature permet de choisir le mieux adapte au cas de la condensation de fluides frigorigenes. Par la suite, afin de mettre a disposition des fabricants et utilisateurs d'echangeurs les principaux resultats de ce travail, le logiciel cetuc a ete etendu au cas des condenseurs de type tema x

Mansur, Sergio Said. "Amélioration des échangeurs thermiques tubulaires par l'utilisation d'inserts hélicoïdaux à l'extérieur des tubes." Grenoble 1, 1993. http://www.theses.fr/1993GRE10192.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Ce travail propose une etude numerique et experimentale du comportement thermohydraulique des echangeurs multitubulaires munis de bandes vrillees a l'exterieur des tubes. Des lois de frottement et d'echange thermique au sein de cette geometrie ont ete determinees experimentalement et programmees dans le logiciel trio developpe au commissariat a l'energie atomique, cea , avec une modelisation du type milieu poreux. Des mesures de pression et de vitesse, ainsi que des visualisations de l'ecoulement ont ete realisees sur un echangeur construit en plexiglas transparent. Les resultats obtenus dans cette etape ont permis d'evaluer la distribution du debit a l'interieur de l'appareil et de degager les elements necessaires a la validation des calculs. L'adequation du modele pour une description macroscopique de l'ecoulement a ete confirmee par des nombreuses comparaisons entre donnees numeriques et experimentales. Une analyse comparative entre differents types d'echangeurs, realisee a l'aide de la simulation, a mis en evidence la performance thermohydraulique satisfaisante de ce nouveau type d'echangeur. Enfin, l'aspect de la diffusion turbulente a l'interieur du faisceau tubulaire a ete aborde par une experience simple de visualisation. D'un point de vue qualitatif, ces essais ont clairement montre que la presence des inserts favorise le melange et la dispersion des proprietes transferables au sein du fluide, qualifiant ainsi les bandes helicoidales en tant de promoteurs de turbulence

Adom, Ebenezer. "Investigation of boiling heat transfer on small diameter tubes and tube bundles." Thesis, Heriot-Watt University, 2007. http://hdl.handle.net/10399/2067.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Boiling heat transfer on the outside of small diameter tubes in the range of 1.8-3.0mm has been investigated. Pool boiling was investigated at nominal atmospheric pressure for each of the tubes iIi isolation. The experiment was varied by investigating the effect of bubbles from a second tube mounted below by varying the heat flux on the upper tube. The upper tube diameter was changed from 3.00 to 2.32 and 1.83mm and in each case the lower tube was 3.00mm. Experimental results showed that the upper tube heat transfer coefficient was enhanced due to the combined mechanism of translating bubbles and turbulent convection at low to moderate heat fluxes. A compact tube bundle made up of 30 stainless steel tubes of outer diameter 3nun, pitch diameter ratio 1.5 and heating length of 50nun was designed to. permit the measurement of flow boiling heat transfer coefficient from tubes within the bundle. The heat flux tested was in the range of 4-21 kW/m2 and mass flux of 5.6-32.8 kg/m2s using distilled water, R-l13 and Flutec PPI at nominal atmospheric pressure as the working fluids. Results obtained showed that the heat transfer coefficient was predominantly dependent on the heat flux as opposed to mass flux. Macro scale models were compared with the experimental results and none of these models predicted the experimental results well. The Confinement number (Co) developed for flow boiling inside micro channels was applied to compact tube bundles and it was shown that confinement is expected ~o be significant for Co>0.63. Photographic studies. also showed that the diameter of the bubbles that were generated within the,bundle were greater than the tube diameter. As such, the sliding bubbles mechanism played less significant role in contributing to the heat transfer coefficient. The recent three-state correlation developed by Thome et al for flow boiling .he.at transfer in micro .channels was modified to predict the experimental results obtained using a compact tube bundle and it has been shown that the thin film evaporation was the dominant mechanism compared to the nucleate boiling. The results from the twin tube and compact bundle arrangement showed two regions coexist at any point in time; that part of the tube covered with liquid subject to nucleate boiling and the other part completely enveloped with vapour. This latter part is designated by the introduction of a factor p and this has been demonstrated experimentally and theoretically corroborated by a model based on a liquid part (i-p) and vapour part p.

Більше джерел

Книги з теми "Bundle of tubes":

Mazzone, Robert Walter. Enhanced condensation of R-113 on a small bundle of horizontal tubes. Monterey, Calif: Naval Postgraduate School, 1991.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Sungiae, Cho, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research., Han ơguk Cho llyo k Kongsa. Research Center., and Han ơguk Wo njaryo k Anjo n Kisurwo n., eds. Assessment of CCFL model of RELAP5/MOD3 against simple verticle tubes and rod bundle tests. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

J, Pavli Albert, and United States. National Aeronautics and Space Administration., eds. Advanced tube-bundle rocket thrust chamber. [Washington, D.C.]: NASA, 1990.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

J, Pavli Albert, and United States. National Aeronautics and Space Administration., eds. Advanced tube-bundle rocket thrust chamber. [Washington, D.C.]: NASA, 1990.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

J, Pavli Albert, and United States. National Aeronautics and Space Administration., eds. Advanced tube-bundle rocket thrust chamber. [Washington, D.C.]: NASA, 1990.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Stasiulevičius, J. Heat transfer of finned tube bundles in crossflow. Edited by Skrinska A, Zhukauskas A. A. 1923-, and Hewitt G. F. Washington: Hemisphere Pub. Corp., 1988.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Mabrey, Burlin Davis. Condensation of refrigerants on small tube bundles. Monterey, Calif: Naval Postgraduate School, 1988.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Dzi͡ubenko, B. V. Unsteady heat and mass transfer in helical tube bundles. New York: Hemisphere Pub. Corp., 1990.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

J, Pavli Albert, Malone Glenn A, and United States. National Aeronautics and Space Administration., eds. New method of making advanced tube-bundle rocket thrust chambers. [Washington, DC]: National Aeronautics and Space Administration, 1990.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Chilman, Scott V. Nucleate boiling characteristics of R-113 in a small enhanced tube bundle. Monterey, Calif: Naval Postgraduate School, 1991.

Знайти повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Більше джерел

Частини книг з теми "Bundle of tubes":

Wan, Shengwu, and Xueyuan Cheng. "Finite Element Analysis of Steel Tube Bundle Composite Shear Wall with Different Constructions." In Lecture Notes in Civil Engineering, 295–302. Singapore: Springer Nature Singapore, 2023. http://dx.doi.org/10.1007/978-981-99-1748-8_25.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

AbstractIn order to study the seismic performance of the steel tube bundle composite shear wall with different constructions. Based on the failure tests of three composite shear wall specimens without steel tube bundle end, with studs and stiffener, a feasible numerical model is established by ABAQUS. The hysteresis curve and energy dissipation coefficient, skeleton curve and ductility of the shear wall were further analyses by varying the axial compression ratio and the spacing of the internal diaphragm. The results show that the stud group and the stiffener group can effectively improve the horizontal bearing capacity, energy dissipation capacity, bearing capacity and ductility of the shear wall. Under the condition of low axial compression ratio, the horizontal bearing capacity of the member with stud is increased by 6.3%; Under the condition of high axial compression ratio, the horizontal bearing capacity of members with stiffeners is increased by 4.5%; The change of axial compression ratio and the spacing between inner diaphragms of shear walls with stiffeners has little effect on their energy dissipation capacity and ductility.

Gnielinski, Volker. "G7 Heat Transfer in Cross-flow Around Single Rows of Tubes and Through Tube Bundles." In VDI Heat Atlas, 725–30. Berlin, Heidelberg: Springer Berlin Heidelberg, 2010. http://dx.doi.org/10.1007/978-3-540-77877-6_40.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Porter, R., and D. V. Evans. "Trapped Modes about Tube Bundles in Waveguides." In IUTAM Symposium on Diffraction and Scattering in Fluid Mechanics and Elasticity, 87–94. Dordrecht: Springer Netherlands, 2002. http://dx.doi.org/10.1007/978-94-017-0087-0_10.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Shakouchi, Toshihiko, Takeshi Kitamura, Koichi Tsujimoto, and Toshitake Ando. "Interaction Between Water or Air-Water Bubble Flow and Tube Bundle—Effects of Arrangement of Tube Bundle and Void Fraction." In Fluid-Structure-Sound Interactions and Control, 111–16. Singapore: Springer Singapore, 2018. http://dx.doi.org/10.1007/978-981-10-7542-1_17.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Buxmann, J. "Pressure Losses in Tube Bundles of Close Spacings." In Design and Operation of Heat Exchangers, 174–79. Berlin, Heidelberg: Springer Berlin Heidelberg, 1992. http://dx.doi.org/10.1007/978-3-642-84450-8_16.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Gelbe, Horst, and Samir Ziada. "O2 Vibration of Tube Bundles in Heat Exchangers." In VDI Heat Atlas, 1553–86. Berlin, Heidelberg: Springer Berlin Heidelberg, 2010. http://dx.doi.org/10.1007/978-3-540-77877-6_111.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Jensen, Michael K. "Boiling on the Shellside of Horizontal Tube Bundles." In Two-Phase Flow Heat Exchangers, 707–46. Dordrecht: Springer Netherlands, 1988. http://dx.doi.org/10.1007/978-94-009-2790-2_24.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Abrahams, I. David, and Gregory A. Kriegsmann. "Electromagnetic Wave Propagation Through Small Diameter Tube Bundles." In Mathematical and Numerical Aspects of Wave Propagation WAVES 2003, 417–22. Berlin, Heidelberg: Springer Berlin Heidelberg, 2003. http://dx.doi.org/10.1007/978-3-642-55856-6_67.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Tang, Jie, Mao Cheng, Wenhong Cao, and Zhangwei Ling. "Failure Risk and Control of Nitrogen Trifluoride Tube-Bundle Container." In Advances in Intelligent Systems and Computing, 374–81. Cham: Springer International Publishing, 2020. http://dx.doi.org/10.1007/978-3-030-43306-2_53.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Ayob, M. Adnan, Sia Hua Jiuh, A. R. Othman, and M. Mohammad. "Assessment of Heat Exchanger Tube Bundle Using STELLAR: Industrial Case Study." In Lecture Notes in Mechanical Engineering, 221–28. Singapore: Springer Nature Singapore, 2024. http://dx.doi.org/10.1007/978-981-99-5946-4_17.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Тези доповідей конференцій з теми "Bundle of tubes":

Monde, Masatsugu, Naoki Ono, Tomohito Nakamori, Kazuo Hirota, Masahito Matsubara, Tomonori Mineno, and Koshi Taguchi. "Seismic Response of Tubes Vibrating Independently in In-Plane Direction for U-Shaped Tube Bundle With Triangular Arrays in Steam Generators." In ASME 2023 Pressure Vessels & Piping Conference. American Society of Mechanical Engineers, 2023. http://dx.doi.org/10.1115/pvp2023-105872.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Abstract Ensuring a complete integrity of steam generators’ tubes during earthquakes is critical. In order to predict the vibration behavior of tube bundle in in-plane direction, seismic tests for U-shaped tube bundle with square arrays had been carried out. During the tests, vibrations were observed in the tube bundle at the location where the tubes and the AVBs vibrate as a whole structure. Independent vibrations for some tubes were also observed at the location where the tubes slide with the AVBs and impact with the adjacent tubes. As for the seismic design, carrying out an evaluation of the tube stress for independent vibrations was sufficient, because the maximum stress of the tubes was much larger than that of the tube bundle vibration. Since tube bundles with triangular arrays have different tube pitches, seismic excitation tests were carried out for this study, to grasp the vibration characteristics of the tubes in in-plane direction. Independent vibrations were observed for some tubes during the tests. The effects of the excitation level, the dominant frequency of excitation wave and the bending radius on independent vibration characteristics were investigated. The damping ratio of independent vibrations is mainly caused by friction force at low velocity, and by impact force with adjacent tube at high velocity. Tube stress of the independent vibration was calculated using the minimum damping ratio obtained from the tests. It was concluded that the calculation can conservatively evaluate the stress of tubes vibrating independently by comparing with the test results.

Ma, Zhixian, Jili Zhang, and Dexing Sun. "Inundation Effect and Its Elimination in Shell and Tube Condenser." In 2010 14th International Heat Transfer Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/ihtc14-23358.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Inundation effect, decrease of condensation heat transfer coefficient (CHTC) induced by both falling condensate from the neighboring tubes above and condensing condensate form the vapor, significantly affects the CHTC of tube bundles composed of smooth and enhanced tubes. This paper experimentally studied the inundation effect of smooth tube and three kinds of enhanced tubes (3D-A, 3D-B and 2D-A), put forward a scheme to eliminate the inundation effect caused by falling condensate and check it by experimental investigation. HFC134a and HFC245fa (substitutes of CFC12 and CFC11, respectively) were condensed in the experiment. Nominal diameter and active length of each test tube is 19.05mm and 500mm, respectively. Diversion ducts were fixed into the test tube bundle to eliminate tube row effect (part of the inundation effect caused by the falling condensate). Drainage strip was equipped on the test tubes to abate the inundation effect induced by condensed condensate. The (These) experimental results show: (1) Inundation effect of HFC 134a and HFC245fa on smooth tube bundle is not as severe as that predicted by Kern’s model. (2) 3D-B enhanced tube is dramatically affected by the inundation effect caused by falling condensate; (3) The equipped diversion ducts can eliminate tube row effect and improve the CHTC of tube bundles composed of smooth and 3D-B tubes. (4) The equipped drainage strip can further enhance the CHTC of 3D-A and 2D-A tubes in the tube bundle.

Hirota, Kazuo, Masatsugu Monde, Naoki Ono, Tomohito Nakamori, Masahito Matsubara, Tomonori Mineno, and Koshi Taguchi. "Considering Gaps Between Tubes and AVBs for U-Shaped Tube Bundle in Steam Generators Using Seismic Linear Analysis Method." In ASME 2023 Pressure Vessels & Piping Conference. American Society of Mechanical Engineers, 2023. http://dx.doi.org/10.1115/pvp2023-102942.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Abstract Ensuring seismic resistance of the tube bundle of steam generators is very important. In order to predict the vibration behavior of the tube bundle, a linear analysis method was developed by modeling all the components of the tube bundle such as tubes and Anti-Vibration Bars (AVB). First natural frequency and its seismic response calculated using the linear analysis were very consistent with the seismic test results. However, since the calculated tube strain distribution was smaller than the results obtained from the test, we developed a nonlinear analysis model that can take into account gaps between tubes and AVBs. Natural frequencies and seismic response, however, cannot be obtained based on this nonlinear analysis. In seismic response evaluations, since focusing on the first order mode of the tube bundle is important, the strain of the tubes was assessed by simulating the deformation of the first order mode, based on a static analysis that uses horizontal inertial acceleration so that the seismic response can be determined by the linear analysis model. In this study, an improved linear analysis model was developed in which tubes and AVBs were connected by linear springs only at contact points. A nonlinear analysis model was used to grasp contact points when the tube bundle was deformed due to seismic load. First natural frequency and its stress distribution in the tube array calculated using the improved linear analysis model were very consistent with the test results obtained from U-shaped tube bundles with both triangular and square arrays. Therefore, it has been concluded that the improved linear analysis model can be applied to seismic analysis for both arrays in steam generator.

Chen, Tailian. "Prediction of Bundle Shell Side Condensation Heat Transfer Coefficient." In ASME 2008 Heat Transfer Summer Conference collocated with the Fluids Engineering, Energy Sustainability, and 3rd Energy Nanotechnology Conferences. ASMEDC, 2008. http://dx.doi.org/10.1115/ht2008-56125.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Prediction of condenser bundle performance is of great interest to chiller design engineers and tube developers as well. Depending on their locations in a condenser bundle, tubes are subjected to inundation or flooding of condensate coming from those above them. The tubes located in the top portion of the bundle are not or slightly inundated whereas the tubes located deep in the bundle experience larger degree of inundation; those in the bundle bottom are the most severely inundated. For a condenser bundle to have good performance, it is necessary for the tubes to perform well in both non-inundated and inundated conditions. In this paper, the outside condensation heat transfer coefficient and its sensitivity to inundation for a condenser tube of enhanced 3-dimensional (3D) outside fins were measured. Based on the single tube measurements, shell side condensation performance of a condenser bundle was predicted. The predicted bundle outside heat transfer coefficient has a reasonable agreement with that of a condenser tested in a 500-ton chiller.

Khushnood, Shahab, Zaffar M. Khan, M. Afzaal Malik, Zafar Ullah Koreshi, and Mehmood Anwer Khan. "Vibration Analysis of a Multispan Tube in a Bundle." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22210.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Nuclear and process industry has seen tube bundle failures more frequently in recent years. There is some concern that the practice of structural configuration has not advanced as rapidly as thermal design of heat exchangers. Catastrophic vibration of tube in a bundle can be avoided if the tube natural frequency is kept well above the estimated existing turbulent buffeting frequencies. Flow distribution and partial admission in to the tube bundle due to upstream piping further complicates the system. In this paper, tube in a bundle has been modeled as a beam on multiple supports. Effects of damping and motion of boundaries have also been considered. Governing equations have been solved analytically for natural as well as forced vibrations. The model has been extended for a bundle of tubes by developing and implementing a computer code. Subsequent experimental verification of results on a research heat exchanger bundle has been carried. The proposed model is expected to prove a useful guide in predicting the vibration behavior of tube bundles.

Chu, C. M., and J. M. McNaught. "TUBE BUNDLE EFFECTS IN CROSSFLOW CONDENSATION ON LOW-FINNED TUBES." In International Heat Transfer Conference 10. Connecticut: Begellhouse, 1994. http://dx.doi.org/10.1615/ihtc10.490.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Gylys, Jonas, Stasys Sinkunas, Tadas Zdankus, and Vidmantas Giedraitis. "Different Type Tube Bundle Heat Transfer to Vertical Foam Flow." In ASME 2007 5th International Conference on Nanochannels, Microchannels, and Minichannels. ASMEDC, 2007. http://dx.doi.org/10.1115/icnmm2007-30070.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Gas-liquid foam due to especially large inter-phase contact surface can be used as a coolant. An experimental investigation of the staggered and in-line tube bundles’ heat transfer to the vertically upward and downward laminar foam flow was performed. The experimental setup consisted of the foam generator, vertical experimental channel, tube bundles, measurement instrumentation and auxiliary equipment. It was determined dependency of heat transfer intensity on flow parameters: flow velocity, direction of flow, volumetric void fraction of foam and liquid drainage from foam. Apart of this, influence of tube position in the bundle to heat transfer was investigated. Foam flow structure, distribution of the foam’s local void fraction and flow velocity in cross-section of the channel were the main factors which influenced on heat transfer intensity of the different tubes. Experimental investigation showed that the heat transfer intensity of the frontal and further tubes of the bundles to vertical foam flow is different in comparison with one-phase fluid flow. The results of the experimental investigation are presented in this paper.

King, Krysten, Amjad Farah, Sahil Gupta, Sarah Mokry, and Igor Pioro. "Comparison of Three-Rod Bundle Data With Existing Heat-Transfer Correlations for Bare Vertical Tubes." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29991.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Many heat-transfer correlations exist for bare tubes cooled with SuperCritical Water (SCW). However, there is very few correlations that describe SCW heat transfer in bundles. Due to the lack of extensive data on bundles, a limited dataset on heat transfer in a SCW-cooled bundle was studied and analyzed using existing bare-tube correlations to find the best-fit correlation. This dataset was obtained by Razumovskiy et al. (National Technical University of Ukraine “KPI”) in SCW flowing upward in a vertical annular channel (1-rod channel) and tight 3-rod bundle consisting of tubes of 5.2-mm outside diameter and 485-mm heated length. The heat-transfer data were obtained at pressures of 22.5, 24.5, and 27.5 MPa, mass flux within a range from 800 to 3000 kg/m2s, inlet temperature from 125 to 352°C, outlet temperature up to 372°C and heat flux up to 4.6 MW/m2. The objective of this study is to compare bare-tube SCW heat-transfer correlations with the data on 1- and 3-rod bundles. This work is in support of SuperCritical Water-cooled Reactors (SCWRs) as one of the six concepts of Generation-IV nuclear systems. SCWRs will operate at pressures of ∼25MPa and inlet temperatures of 350°C.

Revankar, Shripad T., and Gavin Henderson. "Effects of Tube Diameter, Length and Tube Numbers on Condensation of Steam in Vertical Tube Condenser." In ASME 2009 International Mechanical Engineering Congress and Exposition. ASMEDC, 2009. http://dx.doi.org/10.1115/imece2009-10632.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

A heat and mass analogy study was performed for the steam condensation in a vertical tube where steam is completely condensed. In the analysis a single tube, tube bundle with four tubes and two different diameter tubes were considered. The two condensing tubes of same height (0.9m) but different inside diameters, 26.6mm and 52.5mm, were used whereas the tube bundle was made of four tubes of height 1.8 m and 52.5 mm diameter. The results showed that the operating pressure is uniquely determined by inlet steam flow rate for the complete condensation. The condensation heat transfer rate increases and the condensation heat transfer coefficient decreases with the system pressure. The condensation heat transfer coefficients (HTC) were obtained as function various parameters such as different primary pressure (150–450 kPa) and inlet steam flow rate, single tube and tube bundle and tube diameters. Comparison with experimental condensation rates for single tube of 26.6 mm and 52.5 mm and four tube bundle of tube diameter 52.5 mm were made and the agreement was good. The effects of these parameters to condensation performance were evaluated.

Hirota, Kazuo, Masatsugu Monde, Naoki Ono, Tomohito Nakamori, Masahito Matsubara, Tomonori Mineno, and Koshi Taguchi. "Seismic Test and Seismic Response Analysis of U-Shaped Tube Bundle With Triangular Arrays in Steam Generator." In ASME 2022 Pressure Vessels & Piping Conference. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/pvp2022-83643.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Abstract Ensuring a complete integrity of steam generators’ tubes during earthquakes is critical. So far, excitation tests have been conducted for various square array tube bundles in order to grasp vibration behavior during seismic excitation. A seismic analysis method using a simple model has been developed and subsequently verified by comparing the results against those of the above mentioned tests. In this study, seismic excitation tests were carried out for a U-shaped tube bundle with a triangular close-packed array using a full-scale test specimen as the triangular tube array with thinner anti-vibration bars (AVBs) has different vibration characteristics compared with a squared array one. Natural frequencies, modes and stress distribution in the tube bundle, obtained during the experiment, were applied in order to verify the seismic analysis method through the use of a linear analysis model with all tubes and AVBs connected to each other by linear springs as well as with a nonlinear analysis model with gap elements to simulate contact and sliding between all tubes and AVBs. The vibration displacement of the top of the tube bundle calculated by the linear model were in good agreement with the test result. Stress distribution in the tube array calculated using the nonlinear model were in good agreement with the test result. It has been concluded that the linear and nonlinear analysis models are applicable to seismic analysis including for the case of a U-shaped triangular tube array in a steam generator.

Звіти організацій з теми "Bundle of tubes":

Cho, S., N. Arne, B. D. Chung, and H. J. Kim. Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests. International Agreement Report. Office of Scientific and Technical Information (OSTI), June 1993. http://dx.doi.org/10.2172/10168956.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Ashcroft, J., and D. Kaminski. Cross-Stream Thermal Diffusion in a Staggered Tube Bundle with Corrosion. Office of Scientific and Technical Information (OSTI), September 1996. http://dx.doi.org/10.2172/766961.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Chen, S., and S. Chandra. Fluidelastic instabilities in tube bundles exposed to nonuniform crossflow. Office of Scientific and Technical Information (OSTI), June 1989. http://dx.doi.org/10.2172/5171700.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Sindt, Charles F. Orifice meter performance downstream of a tube bundle flow conditioner, elbows, and a tee. Gaithersburg, MD: National Bureau of Standards, 1990. http://dx.doi.org/10.6028/nist.tn.1344.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

George and Delgado. PR-015-06601-R01 Evaluation of Clamp-on Ultrasonic Meters as Field-Portable Diagnostic Tool. Chantilly, Virginia: Pipeline Research Council International, Inc. (PRCI), December 2007. http://dx.doi.org/10.55274/r0010702.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

This study has continued work begun in 2005 to evaluate the use of commercially-available clamp-on ultrasonic meters (USMs) in diagnosing natural gas flow conditions that can produce measurement errors in traditional natural gas meters. In this project, a prototype multi-array clamp-on USM and a commercially available two-path clamp-on USM were mounted on a conventional orifice meter run with a 19-tube bundle flow straighter subjected to well-conditioned flow and a series of adverse flow conditions. Measurements from the clamp-on meters were compared to measurements from the orifice meter under adverse conditions. The objectives of the study were to determine the ability of the clamp-on meters to diagnose abnormal flow conditions that can produce measurement errors in conventional orifice meter configurations, identify the flow profiles within the meter run, and quantify the orifice meter measurement error.

Brockmeyer, Landon, Elia Merzari, Jerome M. Solberg, Kostas Karazis, and Yassin Hassan. High Fidelity Simulation and Validation of Crossflow through a Tube Bundle and the Onset of Vibration. Office of Scientific and Technical Information (OSTI), April 2019. http://dx.doi.org/10.2172/1514804.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Kegel, W. Second-generation pressurized fluidized bed combustion plant: Phase 1, Task 2 topical report: Grimethorpe tube bundle E'' wastage evaluation. Office of Scientific and Technical Information (OSTI), August 1989. http://dx.doi.org/10.2172/6990942.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Hawley. PR-015-11707-R01 Test Diagnostic Methods for Turbine Gas Meters. Chantilly, Virginia: Pipeline Research Council International, Inc. (PRCI), July 2013. http://dx.doi.org/10.55274/r0010671.

Повний текст джерела

Стилі APA, Harvard, Vancouver, ISO та ін.

Анотація:

Similar to most metering technologies, turbine meters are known to be affected by abnormal flow or abnormal mechanical conditions which can cause bias in flow measurement. These types of flow conditions include blockage at the flow meter or straightening vanes, grime or liquid contamination on the internal meter components, damage to the internal meter components, and pulsation in the flow. With the introduction of ultrasonic and Coriolis meters for gas applications, the natural gas industry has embraced the concept of meters with embedded diagnostic capabilities. These capabilities allow the detection of potential problems with the flow behavior or meter condition that may lead to measurement error. Diagnostic measurements also exist for turbine meters. Some turbine meter manufacturers provide techniques for diagnosing proper meter performance through approaches that include unique design attributes (e.g., dual-rotors) or by monitoring the characteristics (shape, timing, etc.) of the pulses produced as blades pass a sensor. Various analog and digital signal analysis methods exist to interpret the output pulse characteristics to determine meter condition attributes such as bent blades and bearing wear. The objective of this research was to assess, through flow testing, the ability of various diagnostic methods to detect abnormal flow and abnormal mechanical conditions for both single and dual-rotor turbine meters. A secondary objective was to determine the amount of flow measurement error that could be present for the various flow conditions that were tested. The approach was to test three different diagnostic methods on a single-rotor and dual-rotor turbine meter at the Metering Research Facility at Southwest Research Institute. The selected diagnostic methods were the Smith MeterTM AccuLERT II from FMC Technologies, TurbinScope from Elster-Instromet, and The Turbo Corrector from Mercury Instruments. Tests were performed under controlled conditions and were designed to determine the ability of the selected diagnostics to detect various levels of flow meter or tube bundle blockage, grime buildup on the rotor or rotor bearings, damage to the rotor, or flow pulsations.