Academic literature on the topic 'Subcooled Boiling Flow'

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Journal articles on the topic "Subcooled Boiling Flow"

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Kandlikar, Satish G., and Murat Bulut. "An Experimental Investigation on Flow Boiling of Ethylene-Glycol/Water Mixtures." Journal of Heat Transfer 125, no. 2 (March 21, 2003): 317–25. http://dx.doi.org/10.1115/1.1561816.

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Mixtures of ethylene glycol and water are used in cooling the engines in automotive applications. Heat is transferred essentially under subcooled flow boiling conditions as the mixture flows over the hot surfaces, which are at temperatures well above the local saturation temperature of the mixture. Very little information is available in the literature on the subcooled flow boiling characteristics of this mixture. The present work focuses on obtaining experimental heat transfer data for water and its mixtures containing ethylene-glycol (0 to 40 percent mass fraction, limited by the maximum allowable temperature in the present setup) in the subcooled flow boiling region. The experimental setup is designed to obtain local heat transfer coefficients over a small circular aluminum heater surface, 9.5-mm in diameter, placed at the bottom 40-mm wide wall of a rectangular channel 3-mm×40-mm in cross-section. Available models for (a) subcooled flow boiling of pure liquids and (b) saturated flow boiling of binary mixtures are extended to model the subcooled flow boiling of binary mixtures.
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Boyd, Ronald D., and Xiaowei Meng. "Boiling curve correlation for subcooled flow boiling." International Journal of Heat and Mass Transfer 38, no. 4 (March 1995): 758–60. http://dx.doi.org/10.1016/0017-9310(95)93011-6.

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Lucic, A., and F. Mayinger. "Transportphenomena in subcooled flow boiling." Heat and Mass Transfer 46, no. 10 (October 24, 2010): 1159–66. http://dx.doi.org/10.1007/s00231-010-0713-4.

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Tu, J. Y., G. H. Yeoh, G. C. Park, and M. O. Kim. "On Population Balance Approach for Subcooled Boiling Flow Prediction." Journal of Heat Transfer 127, no. 3 (March 1, 2005): 253–64. http://dx.doi.org/10.1115/1.1857952.

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The capability of using the population balance approach combined with a three-dimensional two-fluid model for predicting subcooled boiling flow is investigated. Experiments were conducted to study the local flow characteristics of subcooled boiling flow and to provide measured local two-phase flow parameters. Calculations were performed using the newly developed population balance boiling model to study the effects of various factors on numerical predication of local two-phase flow parameters in the subcooled boiling regime. Comparison of model predictions against local measurements was made for the radial distribution of the bubble Sauter diameter and void fraction covering a range of different mass and heat fluxes and inlet subcooling temperatures. Additional comparison using recent active nucleation site density models and empirical relationships to determine the local bubble diameter adopted by other researchers was also investigated. Overall, good agreement was achieved between predictions and measurements using the newly formulated population balance approach based on the modified MUSIG (multiple-size-group) model for subcooled boiling and two-fluid model.
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Nguyen, Ngoc Dat, and Van Thai Nguyen. "Performance Comparison of ANN-Based Model and Empirical Correlations for Void Fraction Prediction of Subcooled Boiling Flow in Vertical Upward Channel." Nuclear Science and Technology 11, no. 4 (January 13, 2023): 07–18. http://dx.doi.org/10.53747/nst.v11i4.335.

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The accurate prediction of void fraction parameter in subcooled boiling flow is very important for nuclear safety since it has significant influences on the mass flow rate, the onset of two-phase flow instability, and the heat transfer characteristics in a nuclear reactor core. Many different models and empirical correlations have been established over a variety of input conditions; however, this classical approach could lead to unsatisfactory prediction due to the uncertainties of model parameter and model forms. To cope with these limitations, Artificial Neural Network (ANN) is a powerful machine learning tool for modeling and solving non-linear and complicated physical problems. Therefore, this work is aim at developing an ANN-based model to predict the local void fraction of subcooled boiling flows. The comparison results of the performance between the ANN-based model and empirical correlations for the void fraction prediction of subcooled boiling in vertical upward channel showed the potential use of ANN-based model in the Computational Fluid Dynamics (CFD) codes to accurately simulate the subcooled boiling phenomena.
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Rajabnia, Hossein, Ehsan Abedini, Ali Tahmasebi, and Amin Behzadmehr. "Experimental investigation of subcooled flow boiling of water/TiO2 nanofluid in a horizontal tube." Thermal Science 20, no. 1 (2016): 99–108. http://dx.doi.org/10.2298/tsci130929122r.

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Subcooled flow boiling heat transfer of water/TiO2 nanofluid in a horizontal tube is experimentally investigated. To validate the experimental apparatus as well as the experimental procedure, data for distilled water were compared with the available results on the literature in both single phase and subcooled flow boiling regime. Experimental investigations were carried out at three nanoparticles volumetric concentrations of 0.01%, 0.1%, and 5%. It was found that the nanofluid heat transfer coefficient in single-phase flow regime augments with the nanoparticle concentration. However, in the case of subcooled flow boiling regime the heat transfer coefficient decreases with the nanoparticle volume fractions.
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Kandlikar, S. G. "Heat Transfer Characteristics in Partial Boiling, Fully Developed Boiling, and Significant Void Flow Regions of Subcooled Flow Boiling." Journal of Heat Transfer 120, no. 2 (May 1, 1998): 395–401. http://dx.doi.org/10.1115/1.2824263.

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Subcooled flow boiling covers the region beginning from the location where the wall temperature exceeds the local liquid saturation temperature to the location where the thermodynamic quality reaches zero, corresponding to the saturated liquid state. Three locations in the subcooled flow have been identified by earlier investigators as the onset of nucleate boiling, the point of net vapor generation, and the location where x = 0 is attained from enthalpy balance equations. The heat transfer regions are identified as the single-phase heat transfer prior to ONB, partial boiling (PB), and fully developed boiling (FDB). A new region is identified here as the significant void flow (SVF) region. Available models for predicting the heat transfer coefficient in different regions are evaluated and new models are developed based on our current understanding. The results are compared with some of the experimental data available in the literature.
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Huang, LiDong, and Larry C. Witte. "Highly Subcooled Boiling in Crossflow." Journal of Heat Transfer 123, no. 6 (May 4, 2001): 1080–85. http://dx.doi.org/10.1115/1.1413762.

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Experiments were carried out to determine the influence of fluid flow and liquid subcooling on flow boiling heat transfer of Freon-113 across horizontal tubes. The data cover wide ranges of velocity (1.5 to 6.9 m/s) and extremely high levels of liquid subcooling (29 to 100°C) at pressures ranging from 122 to 509 kPa. Thin-walled cylindrical electric resistance heaters made of Hastelloy-C with diameter of 6.35 mm were used. The azimuthal wall temperature distributions were measured with five thermocouples around the heaters. The data were compared with Chen’s two-mechanism model with modification for subcooled flow boiling. A new nucleate boiling suppression factor for cross flow was developed. The improved model could predict the present data and Yilmaz and Westwater’s (1980) data well with a mean error ratio of 1.02 and standard deviation of 0.17.
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Dedov, A. V. "Peculiarities of boiling in subcooled flow." Thermal Engineering 56, no. 8 (August 2009): 691–99. http://dx.doi.org/10.1134/s0040601509080126.

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Suzuki, Koichi, Akira Oshima, Chungpyo Hong, and Masataka Mochizuki. "Subcooled Flow Boiling in a Minichannel." Heat Transfer Engineering 32, no. 7-8 (June 2011): 667–72. http://dx.doi.org/10.1080/01457632.2010.509770.

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Dissertations / Theses on the topic "Subcooled Boiling Flow"

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Cao, Yang. "STUDY ON BUBBLE BEHAVIORS IN SUBCOOLED FLOW BOILING." 京都大学 (Kyoto University), 2016. http://hdl.handle.net/2433/215532.

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Stumm, Brian J. "An investigation on bubble departure in subcooled flow boiling /." Online version of thesis, 1993. http://hdl.handle.net/1850/11186.

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Prodanovic, Vladan. "Bubble behaviour in subcooled flow boiling at low pressures and flow rates." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 2001. http://www.collectionscanada.ca/obj/s4/f2/dsk3/ftp04/NQ61160.pdf.

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Samaroo, Randy. "The effects of geometric, flow, and boiling parameters on bubble growth and behavior in subcooled flow boiling." Thesis, The City College of New York, 2016. http://pqdtopen.proquest.com/#viewpdf?dispub=10159915.

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Air bubble injection and subcooled flow boiling experiments have been performed to investigate the liquid flow field and bubble nucleation, growth, and departure, in part to contribute to the DOE Nuclear HUB project, Consortium for Advanced Simulation of Light Water Reactors (CASL). The main objective was to obtain quantitative data and compartmentalize the many different interconnected aspects of the boiling process — from the channel geometry, to liquid and gas interactions, to underlying heat transfer mechanisms.

The air bubble injection experiments were performed in annular and rectangular geometries and yielded data on bubble formation and departure from a small hole on the inner tube surface, subsequent motion and deformation of the detached bubbles, and interactions with laminar or turbulent water flow. Instantaneous and ensemble- average liquid velocity profiles have been obtained using a Particle Image Velocimetry technique and a high speed video camera. Reynolds numbers for these works ranged from 1,300 to 7,700.

Boiling experiments have been performed with subcooled water at atmospheric pres- sure in the same annular channel geometry as the air injection experiments. A second flow loop with a slightly larger annular channel was constructed to perform further boiling experiments at elevated pressures up to 10 bar. High speed video and PIV measurements of turbulent velocity profiles in the presence of small vapor bubbles on the heated rod are presented. The liquid Reynolds number for this set of experiments ranged from 5,460 to 86,000. It was observed that as the vapor bubbles are very small compared to the injected air bubbles, further experiments were performed using a microscopic objective to obtain higher spatial resolution for velocity fields near the heated wall. Multiple correlations for the bubble liftoff diameter, liftoff time and bub- ble history number were evaluated against a number of experimental datasets from previous works, resulting in a new proposed correlations that account for fluid prop- erties that vary with pressure, heat flux, and variations in geometry.

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Richenderfer, Andrew Jonathan. "Experimental study of heat flux partitioning in pressurized subcooled flow boiling." Thesis, Massachusetts Institute of Technology, 2018. http://hdl.handle.net/1721.1/119033.

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Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2018.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Cataloged from student-submitted PDF version of thesis.
Includes bibliographical references (pages 133-137).
Understanding of subcooled flow boiling and the critical heat flux (CHF) is of the utmost importance for both safety and profitability of pressurized water nuclear reactors since they are major factors in the determination of the reactor power rating. Motivated by the emergence of a new wall boiling model by Gilman [3] and previous experimental insights from Phillips [12], a first-of-a-kind experimental investigation of pressurized steady-state subcooled flow boiling was conducted using state-ofthe- art diagnostics to gain a unique insight of the relevant mechanisms, including the partitioning of the wall heat flux. Conditions up to 10 bar pressure, 2000 kg/m²s mass flux and 20 K subcooling were explored. High-speed infrared thermometry tools were developed and used to measure the local time-dependent 2-D temperature and heat flux distributions on the boiling surface. These distributions were analyzed to determine fundamental boiling heat transfer parameters such as the nucleation site density, growth and wait times, nucleation frequency, departure diameter as well as the partitioning of the wall heat flux. While established mechanistic models can capture the trends of growth time and wait time with relatively good accuracy, this work reveals current models do not accurately predict the activation and interaction of nucleation sites on the boiling surface. This is a major roadblock, since boiling curves and CHF values obtained in nominally identical environments can be significantly different depending upon the nucleation site density which in turn is determined by the surface properties. The role of evaporation in the partitioning of the heat flux increases monotonically as the average heat flux increases, up to a maximum value of 70%, and is the dominant mechanism at high heat fluxes. At low and intermediate heat fluxes single-phase heat transfer is the dominant mechanism. Traditional heat partitioning models fail to capture these physics, but newer models with a comprehensive and physically consistent framework show promise in predicting the wall heat transfer. The data and understanding produced by this work will be essential for the development and validation of these modeling tools.
by Andrew Jonathan Richenderfer.
Ph. D.
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Tow, Emily Winona. "Bubble behavior in subcooled flow boiling on surfaces of variable wettability." Thesis, Massachusetts Institute of Technology, 2012. http://hdl.handle.net/1721.1/75682.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, 2012.
Cataloged from PDF version of thesis.
Includes bibliographical references (p. 59).
Flow boiling is important in energy conversion and thermal management due to its potential for very high heat fluxes. By improving understanding of the conditions leading to bubble departure, surfaces can be designed that increase heat transfer coefficients in flow boiling. Bubbles were visualized during subcooled nucleate flow boiling of water on a surface of variable wettability. Images obtained from the videos were analyzed to find parameters influencing bubble size at departure. A model was developed relating the dimensions of the bubble at departure to its upstream and downstream contact angles based on a rigid-body force balance between momentum and surface tension and assuming a skewed truncated spherical bubble shape. Both experimental and theoretical results predict that bubble width and height decrease with increasing flow speed and that the width increases with the equilibrium contact angle. The model also predicts that the width and height increase with the amount of contact angle hysteresis and that the height increases with equilibrium contact angle, though neither of these trends were clearly demonstrated by the data. Several directions for future research are proposed, including modifications to the model to account for deviations of the bubbles from the assumed geometry and research into the parameters controlling contact angle hysteresis of bubbles in a flow. Additionally, observations support that surfaces with periodically-varying contact angle may prevent film formation and increase the heat transfer coefficients in both film and pool boiling.
by Emily W. Tow.
S.B.
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Coyle, Carolyn Patricia. "Synthesis of CRUD and its effects on pool and subcooled flow boiling." Thesis, Massachusetts Institute of Technology, 2016. http://hdl.handle.net/1721.1/103652.

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Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, 2016.
This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections.
Cataloged from student-submitted PDF version of thesis.
Includes bibliographical references (pages 127-132).
This work is dedicated to studying the effects of synthetic CRUD (Chalk River Unidentified Deposits) on pool and subcooled flow boiling parameters. Previous pool boiling studies have demonstrated the potential of porous, hydrophilic surfaces to lead to more efficient boiling. CRUD is a naturally occurring porous, hydrophilic layer that forms on fuel rods during reactor operation. As such, CRUD deposition may have large effects on critical heat flux (CHF) and heat transfer coefficient (HTC). An investigation of such effects was conducted as part of the CASL project by creating well-defined and characterized synthetic CRUD with parameters representative of reactor CRUD on indium tin oxide-sapphire heaters. The effects of synthetic CRUD on boiling heat transfer were then experimentally studied, focusing on heat transfer coefficient (HTC), critical heat flux (CHF), nucleation site density, bubble departure frequency, and bubble departure diameter. These heaters were tested in pool and flow boiling facilities in MIT's Reactor Hydraulics Laboratory. Synthetic CRUD was created using layer-by-layer deposition of 100 nm silica nanoparticles to form porous, hydrophilic thick films. Photolithography was used to manufacture posts that were then dissolved to create characteristic boiling chimneys. Features such as thickness, wettability, pore size, and chimney diameter and pitch were verified to be representative of reactor CRUD. Silica nanoparticles were used as a surrogate for reactor CRUD nanoparticle materials (iron and nickel oxides) since they create more stable films. To ensure accurate modeling, independent of material, 10 nm silica nanoparticle and 10 nm iron oxide nanoparticle boiling tests were conducted and found to be similiar. During testing, IR thermography and high-speed video (HSV) are used to obtain two dimensional temperature profiles of the active heater area to quantify properties such as HTC, nucleation site density, bubble departure frequency, and bubble departure diameter. The bubble parameters follow expected trends with mass flux and heat flux. IR/HSV flow data (Chapter 6) has shown that HTC increases with the presence of chimneys, increasing thickness and increasing chimney diameter. However the HTC is relatively unaffected by the chimney pitch and is decreased by the presence of an LbL layer. The boiling curves and CHF data obtained from pool boiling experiments with iron oxide and silica oxide nanoparticles with and without chimneys also confirm these trends. The largest HTC is observed in the case of uncoated heaters, followed by heaters with chimneys, with heaters with an LbL layer without chimneys having the lowest HTC. From pool boiling data, the benefit of a CRUD layer is observed in the enhancement of CHF. The flow boiling trends are further supported by the combination of measured basic bubble parameters according to the heat flux partitioning model. The statistical significance of these trends varies with mass flux. The data generated here may inform advanced models of boiling heat transfer and/or validate existing models.
by Carolyn Patricia Coyle.
S.M.
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Chong, Jen Haw. "Modelling of subcooled flow boiling in a rectangular micro-channel heat sink." Thesis, University of Nottingham, 2018. http://eprints.nottingham.ac.uk/51313/.

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Attaching micro-channel heat sinks operating under flow boiling conditions on heat sources of electronic components is an efficient cooling technique which still requires further improvements of designs. When developing this system, the efficient heat transfer performance is essential, however, this development often entangles with difficulties. The difficulties arise as existing prediction approaches are underdeveloped and inadequate to perform the accurate prediction in wide ranges of operating conditions. This inadequacy persists due to incomplete discoveries of involved mechanisms that involve fluid and dynamics for the heat transfer during the flow boiling. Also, the mechanisms involved in the flow boiling process are complicated, hindering the development of more reliable approaches. By addressing this issue, this study explores and investigates the relating mechanisms. The mechanisms of fluids during the flow boiling of subcooled liquids in micro-channel heat sinks immediately before and during the nucleation of first bubbles were explored in this study. This study then addressed the mechanisms of heat transfer enhancement of flow boiling. Later, this study repeated with different substrate materials of micro-channel heat sinks and working fluids. This study serves the purpose to better understand the involved mechanisms during the flow boiling of subcooled liquids in micro-channel heat sinks for the development of more reliable approaches to predict the heat transfer. This study regarding the mechanisms during the flow boiling in micro-channel heat sinks implemented the numerical model associated with the Volume of Fluid (VOF) in which corresponding governing equations were solved using a computational fluid dynamics (CFD). In this model, computational domains of micro-channel heat sinks in three dimensions that include the sub-domains of solids and fluid were created to consider the conjugate heat transfer for better estimation of data. The data collected in this study were from operating parameters of heat flux, mass flux, and inlet temperature of the micro-channel at 500-3197 kW/m2, 115-389 kg/m2 s, and 23-53°C, respectively. The micro-channel heat sinks operated at the atmospheric pressure, and the corresponding substrate materials chosen were steel, silicon, aluminium and copper, and working fluids selected were water and ethanol. The numerical results agree well with the experimental data from the previous study. The results show that although the bubble nucleation is absent, the heat transfer mechanisms in micro-channels possesses the nucleate boiling characteristic involving the transient conduction with the existence of the phase change process. The heat transfer mechanisms from the phase change process with the incomplete evaporation induce the ascending and descending flows and liquid-vapour mixture on the heating surfaces. From the results, four different modes of heat transfer mechanisms from the phase change process associated with ascending and descending flows and liquid vapour mixture become apparent. The ascending and descending flows on the heating surfaces appear with local increases of pressure gradients near to the heating surfaces facilitating the heat transfer enhancement due to phase change. On the other hand, the liquid-vapour mixture produced from the phase change process impeding the heat transfer. In overall, the heat transfer enhancement due to the phase change at the side surfaces in the micro-channel is more extensive as compared to the bottom surface for each condition tested in this study. Meanwhile, the amount of the liquid-vapour mixture accumulating on the bottom surface is more massive as compared to the side surfaces, leading to the impedance of the heat transfer. These heat transfer mechanisms also persist during flow boiling in micro-channels. The heat transfer enhancement due to phase change from the side and bottom surfaces also varies when employing different operating conditions before and during flow boiling. This study provides better insights for researchers and designers in industries regarding the local mechanisms for the heat transfer during the flow boiling in micro-channel heat sinks. These understandings assist the researchers to develop the more reliable prediction methods to design new and better heat transfer performance of micro-channel heat sinks and avoid repeating experiments which are costly and tedious in procedures.
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Cartwright, Michael D. "Experimental and analytical investigation of the bubble nucleation characteristics in subcooled flow /." Online version ot thesis, 1995. http://hdl.handle.net/1850/12048.

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Najibi, Seyed Hesam. "Heat transfer and heat transfer fouling during subcooled flow boiling for electrolyte solutions." Thesis, University of Surrey, 1997. http://epubs.surrey.ac.uk/773/.

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Books on the topic "Subcooled Boiling Flow"

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Boyd, Ronald D. Subcooled water flow boiling in a horizontal coolant channel at 0.45 MPa for fusion applications. Prairie View, Tx: Texas A & M University, 1989.

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Boyd, Ronald D. Experimental subcooled flow boiling for high heat flux applications. Prarie View, Tex: Prairie View A&M University. Dept. of Mechanical Engineering, 1989.

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Yeoh, Guan Heng. Modelling subcooled boiling flows. New York: Nova Science Publishers, 2008.

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American Society of Mechanical Engineers. Winter Meeting. Fundamentals of subcooled flow boiling: Presented at the Winter Annual Meeting of the American Society of Mechanical Engineers, Anaheim, California, November 8-13, 1992. New York, N.Y: American Society of Mechanical Engineers, 1992.

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Najibi, Seyed Hesam. Heat transfer and heat transfer fouling during subcooled flow boiling for electrolyte solutions. 1997.

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Book chapters on the topic "Subcooled Boiling Flow"

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Kolev, Nikolay Ivanov. "Boiling of subcooled liquid." In Multiphase Flow Dynamics 3, 195–205. Berlin, Heidelberg: Springer Berlin Heidelberg, 2011. http://dx.doi.org/10.1007/978-3-642-21372-4_8.

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Krepper, Eckhard, and Wei Ding. "Review of Subcooled Boiling Flow Models." In Handbook of Multiphase Flow Science and Technology, 1–27. Singapore: Springer Singapore, 2016. http://dx.doi.org/10.1007/978-981-4585-86-6_20-1.

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Celata, Gian Piero. "Critical Heat Flux in Subcooled Flow Boiling." In Energy and Environment, 126–61. Tokyo: Springer Japan, 2001. http://dx.doi.org/10.1007/978-4-431-68325-4_6.

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Celata, Gian Piero, Maurizio Cumo, Andrea Mariani, and Giuseppe Zummo. "Visual Investigation of Boiling Phenomena in CHF Subcooled Flow Boiling." In Applied Optical Measurements, 79–93. Berlin, Heidelberg: Springer Berlin Heidelberg, 1999. http://dx.doi.org/10.1007/978-3-642-58496-1_5.

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Ishii, Mamoru, and Takashi Hibiki. "One-Dimensional Interfacial Area Transport Equation in Subcooled Boiling Flow." In Thermo-Fluid Dynamics of Two-Phase Flow, 475–81. New York, NY: Springer New York, 2010. http://dx.doi.org/10.1007/978-1-4419-7985-8_17.

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Li, Y. Z., G. H. Yeoh, and J. Y. Tu. "Numerical Investigation of Flow Instability in a Low-Pressure Subcooled Boiling Channel." In Computational Fluid Dynamics 2002, 559–64. Berlin, Heidelberg: Springer Berlin Heidelberg, 2003. http://dx.doi.org/10.1007/978-3-642-59334-5_84.

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Yeoh, G. H., S. C. P. Cheung, J. Y. Tu, and M. K. M. Ho. "Modeling Vertical Subcooled Boiling Flows at Low Pressures." In Film and Nucleate Boiling Processes, 349–75. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2011. http://dx.doi.org/10.1520/stp49345t.

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Yeoh, G. H., S. C. P. Cheung, J. Y. Tu, and M. K. M. Ho. "Modeling Vertical Subcooled Boiling Flows at Low Pressures." In Film and Nucleate Boiling Processes, 349–75. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959: ASTM International, 2011. http://dx.doi.org/10.1520/stp153420120016.

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"Subcooled Flow Boiling." In Encyclopedia of Microfluidics and Nanofluidics, 3088. New York, NY: Springer New York, 2015. http://dx.doi.org/10.1007/978-1-4614-5491-5_200264.

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Yang, Yu-Min, and Jer-Ru Maa. "Subcooled Convective Boiling of Aqueous Surfactant Solutions." In Convective Flow Boiling, 105–10. CRC Press, 2019. http://dx.doi.org/10.1201/9780367812089-11.

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Conference papers on the topic "Subcooled Boiling Flow"

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Oshima, Akira, Koichi Suzuki, Chungpyo Hong, and Masataka Mochizuki. "Subcooled Flow Boiling in a Minichannel." In ASME 2009 7th International Conference on Nanochannels, Microchannels, and Minichannels. ASMEDC, 2009. http://dx.doi.org/10.1115/icnmm2009-82105.

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It has been considered that the dry-out is easy to occur in boiling heat transfer for a small channel, a mini or microchannel because the channel was easily filled with coalescing vapor bubbles. In the present study, the experiments of subcooled flow boiling of water were performed under atmospheric condition for a horizontal rectangular channel of which size is 1mm in height and 1mm in width with a flat heating surface of 10mm in length and 1mm in width placed on the bottom of the channel. The heating surface is a top of copper heating block and heated by ceramics heaters. In the high heat flux region of nucleate boiling, about 70 ∼ 80 percent of heating surface was covered with a large coalescing bubble and the boiling reached critical heat flux (CHF) by a high speed video observation. In the beginning of transition boiling, coalescing bubbles were collapsed to many fine bubbles and microbubble emission boiling was observed at higher liquid subcooling than 30K. The maximum heat flux obtained was 8MW/m2 (800W/cm2) at liquid subcooling of higher than 40K and the liquid velocity of 0.5m/s. However, the surface temperature was extremely higher than that of centimeter scale channel. The high speed video photographs indicated that microbubble emission boiling occurs in the deep transition boiling region.
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Ose, Y., T. Kunugi, Liejin Guo, D. D. Joseph, Y. Matsumoto, Y. Sommerfeld, and Yueshe Wang. "Numerical Simulation on Subcooled Pool Boiling." In THE 6TH INTERNATIONAL SYMPOSIUM ON MULTIPHASE FLOW, HEAT MASS TRANSFER AND ENERGY CONVERSION. AIP, 2010. http://dx.doi.org/10.1063/1.3366456.

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Celata, Gian Piero. "CRITICAL HEAT FLUX IN SUBCOOLED FLOW BOILING." In International Heat Transfer Conference 11. Connecticut: Begellhouse, 1998. http://dx.doi.org/10.1615/ihtc11.2750.

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Zheng, Qiang, Puzhen Gao, and Jian Hu. "Bubble Growth During Subcooled Forced Convective Flow Boiling." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16200.

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The inception, growth and collapse of vapor bubbles were observed and measured by using visual method under subcooled flow nucleation. The test section was a single-side heated rectangular channel by the scale of 2×40×700mm and the working fluid was clean water. The working condition was set as: the inlet subcooling Δ Tin = 330 °C, the mass flux m = 694kg/(m2s), the heat flux q = 210kW/m2 and the absolute pressure p = 0.22MPa. A high speed camera was used to record the bubble behaviors at the speed of 5000fps (frame per second). The results showed that the bubble lifetime was from 0.4ms to 2.2ms and the fraction of bubble with short lifetime was bigger than that of long lifetime. The bubble’s average diameter showed a linear relationship with the lifetime and it was also found that the sliding bubble would enhance heat transfer.
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5

Situ, R., J. Y. Tu, Guan Heng Yeoh, Goon Cherl Park, T. Hibiki, and Mamoru Ishii. "BUBBLE DEPARTURE IN FORCED CONVECTIVE SUBCOOLED BOILING FLOW." In Annals of the Assembly for International Heat Transfer Conference 13. Begell House Inc., 2006. http://dx.doi.org/10.1615/ihtc13.p28.220.

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6

Boyd, Ronald D., Xiaowei Meng, Alvin Smith, and Jerry Turknett. "Local subcooled flow boiling model assessment and development." In SPIE's 1993 International Symposium on Optics, Imaging, and Instrumentation, edited by Ali M. Khounsary. SPIE, 1993. http://dx.doi.org/10.1117/12.163802.

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7

Yeoh, G. H., and J. Y. Tu. "A Mechanistic Model for Predicting Subcooled Boiling Flow." In ASME/JSME 2003 4th Joint Fluids Summer Engineering Conference. ASMEDC, 2003. http://dx.doi.org/10.1115/fedsm2003-45571.

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Population balance equations combined with a three-dimensional two-fluid model are employed to predict subcooled boiling flow at low pressure in a vertical annular channel. The MUSIG (MUltiple-SIze-Group) model implemented in CFX4.4 is extended to account for the wall nucleation and condensation in the subcooled boiling regime. Comparison of model predictions against local measurements is made for the void fraction, bubble Sauter diameter and gas and liquid velocities covering a range of different mass and heat fluxes and inlet subcoolings. Good agreement is achieved with the local radial void fraction, bubble Sauter diameter and liquid velocity profiles against measurements. However, significant weakness of the model is evidenced in the prediction of the vapor velocity. Work is in progress to circumvent the deficiency of the extended MUSIG model by the consideration of an algebraic slip model to account for bubble separation.
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8

Bower, Jason S., and James F. Klausner. "Gravity Independent Subcooled Flow Boiling Heat Transfer Regime." In Thermal Sciences 2004. Proceedings of the ASME - ZSIS International Thermal Science Seminar II. Connecticut: Begellhouse, 2004. http://dx.doi.org/10.1615/ichmt.2004.intthermscisemin.720.

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9

Zarate, J. A., R. P. Roy, S. Kang, and Andre Laporta. "Modeling and Simulation of Subcooled Turbulent Boiling Flow." In ASME 2000 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2000. http://dx.doi.org/10.1115/imece2000-1531.

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Abstract Modeling and numerical simulation of turbulent sub-cooled boiling flow of refrigerant-113 through a vertical concentric annular channel with its inner wall heated are reported. The two-fluid model conservation equations were solved. The Reynolds stresses in the liquid phase momentum equation were closed using the gradient transport approximation. The turbulent viscosity was considered to be comprised of shear-induced and bubble-induced components. Boiling at the inner wall was described by a wall heat transfer model which splits the wall heat flux into convective, quenching, and vaporization heat flux components. This model was modified to reflect our measurement of the radial turbulent heat flux in the liquid phase near the wall. In addition, new wall laws for the liquid phase mean temperature and axial velocity were used. The computational results are compared with our measurements wherever possible.
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10

Kandlikar, Satish G. "Heat Transfer Characteristics in Partial Boiling, Fully Developed Boiling, and Significant Void Flow Regions of Subcooled Flow Boiling." In ASME 1997 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 1997. http://dx.doi.org/10.1115/imece1997-0765.

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Abstract Subcooled flow boiling covers the region beginning from the location where the wall temperature exceeds the local liquid saturation temperature to the location where the thermodynamic quality reaches zero, corresponding to the saturated liquid state. Three locations in the subcooled flow have been identified by earlier investigators as the onset of nucleate boiling, the point of net vapor generation, and the location where x = 0 is attained from enthalpy balance equations. The heat transfer regions are identified as the single phase heat transfer prior to ONB, partial boiling (PB), and fully developed boiling (FDB). A new region is identified here as the significant void flow (SVF) region. Available models for predicting the heat transfer coefficient in different regions are evaluated and new models are presented based on our current understanding. The results are compared with some of the experimental data available in the literature.
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Reports on the topic "Subcooled Boiling Flow"

1

Siman-Tov, M., D. K. Felde, J. L. McDuffee, and G. L. Yoder. Experimental study of static flow instability in subcooled flow boiling in parallel channels. Office of Scientific and Technical Information (OSTI), December 1995. http://dx.doi.org/10.2172/234622.

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2

Lee, S. C., and S. G. Bankoff. Prediction of the onset of significant void in transient subcooled flow boiling. Office of Scientific and Technical Information (OSTI), June 1993. http://dx.doi.org/10.2172/10104504.

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3

Dr. Ronald D. Boyd. Local Heat Transfer and CHF for Subcooled Flow Boiling - Annual Report 1993. Office of Scientific and Technical Information (OSTI), July 2000. http://dx.doi.org/10.2172/769387.

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4

Dr. Ronald D. Boyd. Local Heat Transfer and CHF for Subcooled Flow Boiling - Annual Report 1994. Office of Scientific and Technical Information (OSTI), July 2000. http://dx.doi.org/10.2172/769388.

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5

Dr. Ronald D. Boyd. Local Heat Transfer and CHF for Subcooled Flow Boiling - Annual Report 1996. Office of Scientific and Technical Information (OSTI), July 2000. http://dx.doi.org/10.2172/769389.

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6

Dr. Ronald D. Boyd. Local Heat Transfer and CHF for Subcooled Flow Boiling - Annual Report 1997. Office of Scientific and Technical Information (OSTI), July 2000. http://dx.doi.org/10.2172/769390.

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7

Barclay G. Jones. Analysis and Measurement of Bubble Dynamics and Associated Flow Field in Subcooled Nucleate Boiling Flows. Office of Scientific and Technical Information (OSTI), October 2008. http://dx.doi.org/10.2172/951327.

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8

Gehrke, V., and S. G. Bankoff. Stability of forced-convection subcooled boiling in steady-state and transient annular flow. Office of Scientific and Technical Information (OSTI), June 1993. http://dx.doi.org/10.2172/10194741.

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9

Anh Bui, Nam Dinh, and Brian Williams. Validation and Calibration of Nuclear Thermal Hydraulics Multiscale Multiphysics Models - Subcooled Flow Boiling Study. Office of Scientific and Technical Information (OSTI), September 2013. http://dx.doi.org/10.2172/1110336.

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10

Yoo, Jun Soo. Bubble Departure Diameter and Bubble Release Frequency Measurement from TAMU Subcooled Flow Boiling Experiment. Office of Scientific and Technical Information (OSTI), December 2016. http://dx.doi.org/10.2172/1364235.

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