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Статті в журналах з теми "Subcooled Boiling Flow"
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.
Повний текст джерелаBoyd, 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.
Повний текст джерелаLucic, 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.
Повний текст джерелаTu, 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.
Повний текст джерелаNguyen, 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.
Повний текст джерелаRajabnia, 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.
Повний текст джерелаKandlikar, 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.
Повний текст джерелаHuang, 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.
Повний текст джерелаDedov, A. V. "Peculiarities of boiling in subcooled flow." Thermal Engineering 56, no. 8 (August 2009): 691–99. http://dx.doi.org/10.1134/s0040601509080126.
Повний текст джерелаSuzuki, 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.
Повний текст джерелаДисертації з теми "Subcooled Boiling Flow"
Cao, Yang. "STUDY ON BUBBLE BEHAVIORS IN SUBCOOLED FLOW BOILING." 京都大学 (Kyoto University), 2016. http://hdl.handle.net/2433/215532.
Повний текст джерелаStumm, Brian J. "An investigation on bubble departure in subcooled flow boiling /." Online version of thesis, 1993. http://hdl.handle.net/1850/11186.
Повний текст джерелаProdanovic, 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.
Повний текст джерелаSamaroo, 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.
Повний текст джерелаAir 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.
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.
Повний текст джерелаThis 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.
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.
Повний текст джерелаCataloged 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.
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.
Повний текст джерелаThis 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.
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/.
Повний текст джерелаCartwright, 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.
Повний текст джерелаNajibi, 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/.
Повний текст джерелаКниги з теми "Subcooled Boiling Flow"
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.
Знайти повний текст джерелаBoyd, Ronald D. Experimental subcooled flow boiling for high heat flux applications. Prarie View, Tex: Prairie View A&M University. Dept. of Mechanical Engineering, 1989.
Знайти повний текст джерелаYeoh, Guan Heng. Modelling subcooled boiling flows. New York: Nova Science Publishers, 2008.
Знайти повний текст джерелаAmerican 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.
Знайти повний текст джерелаNajibi, Seyed Hesam. Heat transfer and heat transfer fouling during subcooled flow boiling for electrolyte solutions. 1997.
Знайти повний текст джерелаЧастини книг з теми "Subcooled Boiling Flow"
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.
Повний текст джерелаKrepper, 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.
Повний текст джерелаCelata, 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.
Повний текст джерелаCelata, 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.
Повний текст джерелаIshii, 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.
Повний текст джерелаLi, 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.
Повний текст джерелаYeoh, 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.
Повний текст джерелаYeoh, 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.
Повний текст джерела"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.
Повний текст джерелаYang, 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.
Повний текст джерелаТези доповідей конференцій з теми "Subcooled Boiling Flow"
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.
Повний текст джерелаOse, 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.
Повний текст джерелаCelata, 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.
Повний текст джерелаZheng, 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.
Повний текст джерелаSitu, 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.
Повний текст джерелаBoyd, 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.
Повний текст джерелаYeoh, 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.
Повний текст джерелаBower, 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.
Повний текст джерелаZarate, 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.
Повний текст джерелаKandlikar, 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.
Повний текст джерелаЗвіти організацій з теми "Subcooled Boiling Flow"
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.
Повний текст джерелаLee, 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.
Повний текст джерелаDr. 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.
Повний текст джерелаDr. 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.
Повний текст джерелаDr. 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.
Повний текст джерелаDr. 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.
Повний текст джерелаBarclay 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.
Повний текст джерелаGehrke, 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.
Повний текст джерелаAnh 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.
Повний текст джерелаYoo, 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.
Повний текст джерела