Relevant bibliographies by topics / Critical flux

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Critical flux'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "Critical flux"

1

Beier, Søren Prip, and Gunnar Jonsson. "Critical flux determination by flux-stepping." AIChE Journal 56, no. 7 (November 2, 2009): 1739–47. http://dx.doi.org/10.1002/aic.12099.

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Katto, Y. "Critical heat flux." International Journal of Multiphase Flow 20 (August 1994): 53–90. http://dx.doi.org/10.1016/0301-9322(94)90070-1.

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Collado, F. J. "Critical heat flux thermodynamics." Fusion Engineering and Design 61-62 (November 2002): 165–70. http://dx.doi.org/10.1016/s0920-3796(02)00114-x.

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Prasad, Vish, and Arun Kumar Nayak. "PREFACE: CRITICAL HEAT FLUX." Annual Review of Heat Transfer 22, no. 1 (2019): v—vi. http://dx.doi.org/10.1615/annualrevheattransfer.v22.10.

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Tanaka, Futoshi, Kaichiro Mishima, and Takashi Hibiki. "ICONE15-10272 Critical Heat Flux correlation for thin rectangular channels." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_133.

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Chandraker, Dinesh K., Arnab Dasgupta, and Arun Kumar Nayak. "CRITICAL HEAT FLUX: AN OVERVIEW." Annual Review of Heat Transfer 22, no. 1 (2019): 1–28. http://dx.doi.org/10.1615/annualrevheattransfer.2020033343.

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Carlson, R. W. "Spreading of critical heat flux region during testing for onset of critical heat flux." Annals of Nuclear Energy 16, no. 2 (January 1989): 49–62. http://dx.doi.org/10.1016/0306-4549(89)90029-7.

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MONDE, Masanori, Yuichi MITSUTAKE, and Satoshi KUSUMOTO. "Critical Heat Flux in Vertical Two Phase Concentric Tube Thermosyphon. Enhancement of Critical Heat Flux." Transactions of the Japan Society of Mechanical Engineers Series B 64, no. 628 (1998): 4193–99. http://dx.doi.org/10.1299/kikaib.64.4193.

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Senoussi, S., A. Kilic, P. Manuel, R. Gagnon, L. Taillefer, and H. Traxler. "Anomalous flux pinning and flux creep near the critical state." Physica C: Superconductivity 264, no. 3-4 (June 1996): 172–78. http://dx.doi.org/10.1016/0921-4534(96)00253-5.

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van der Marel, Perry, Arie Zwijnenburg, Antoine Kemperman, Matthias Wessling, Hardy Temmink, and Walter van der Meer. "An improved flux-step method to determine the critical flux and the critical flux for irreversibility in a membrane bioreactor." Journal of Membrane Science 332, no. 1-2 (April 2009): 24–29. http://dx.doi.org/10.1016/j.memsci.2009.01.046.

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Dissertations / Theses on the topic "Critical flux"

1

Yang, Jun. "Effect of non-uniform axial heat-flux distribution on critical heat flux." Thesis, University of Ottawa (Canada), 2004. http://hdl.handle.net/10393/26816.

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An experimental study of the effect of axial flux distribution (AFD) on critical heat flux (CHF) was conducted in directly heated tubes at the Freon-equivalent CANDU reactor conditions of interest. CHF measurements were obtained on test sections with four nonuniform AFD profiles as well as a uniform AFD profile using HFC-134a as a test fluid. Each of the non-uniform AFD test sections had a stepped cosine heat flux profile with approximately 16 heat flux steps. The test conditions covered a pressure range of 1662 to 2389 kPa, a mass flux range of 2827 to 4648 kg m-2 s -1 and an inlet quality range of -0.909 to -0.002. The results showed that the AFD has a strong effect on CHF at high dryout qualities. (Abstract shortened by UMI.)
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Manning, Jonathan Paul. "Critical heat flux in non-circular channels." Thesis, Imperial College London, 2018. http://hdl.handle.net/10044/1/61534.

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In the design of nuclear reactors adequate cooling must be demonstrated for all operational states as well as during and after design basis accidents. A key aspect of this design activity is the prediction of the Critical Heat Flux (CHF). The focus of the work in this thesis was the prediction of CHF in non-circular channels. The Look Up Table was used to analyse several burnout studies for non-circular channels in the literature and was found to be a poor predictive tool for these geometries. A conventional phenomenological model developed for round tubes was also shown to give poor predictions, with a mean error of 25% and root mean square error of 31%. Phenomenological modelling requires correlations for the mass transfer processes in annular flow. Deposition rates for annular flow in rectangular channels have been determined by an analysis of upstream burnout data. This showed good agreement with the rates in round tubes and validated this aspect of the phenomenological approach. The conventional one-dimensional phenomenological model was extended to include a variation in film thickness around the periphery. This model was fitted to experimental data from the literature for burnout in asymmetrically heated tubes. The low mean and root mean square errors, 0.8% and 3.0% respectively, confirmed the principle of the model. A flow visualisation rig has been designed and successfully operated to produce a flow-regime map for a rectangular channel of 25 mm by 2.5 mm. This map showed that the gas momentum flux required to cause annular flow was higher than that in round tubes. A wide range of annular flow conditions were observed and shown to be generally consistent with the phenomenological modelling approach. However it was seen that there were novel flow features that will need to be accounted for when predicting CHF in these geometries.
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Thompson, Jordan Lee. "Direct Measurement of Boiling Water Heat Flux for Predicting and Controlling Near Critical Heat Flux." Thesis, Virginia Tech, 2013. http://hdl.handle.net/10919/23091.

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A novel method for measuring heat flux of boiling water is designed and built to study critical heat flux (CHF) and observe the response of a heat flux sensor when CHF occurs. A high temperature heat flux sensor is embedded in the wall of a pipe to get a direct measurement of the surface heat flux and sensor temperature. By submerging the pipe in water and applying a controlled heat flux to the inside diameter over the area where the sensor is located, boiling is created on the outer surface while measuring the heat flux. The heat flux is gradually increased up to CHF and the heat flux response is observed to determine if the heat flux sensor could sense CHF when it occurred. The heat flux sensor is able to consistently measure the value for CHF, which is approximately 510 kW/m" for this system. It is also observed during the experiments that the heat flux response undergoes an inflection of the heat transfer coefficient at a consistent temperature just before reaching CHF. This observed inflection caused the heat flux response to deviate from its cubic relationship with the temperature and drastically increase for a very small change in temperature. This inflection response can be used as an indication for approaching CHF and can also be used to approximate its value without prior knowledge of when it occurs.
Master of Science
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Joober, Khaled. "The effect of flow geometry on critical heat flux." Thesis, University of Ottawa (Canada), 1993. http://hdl.handle.net/10393/6544.

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An extensive and systematic literature review on the effect of flow geometry on the Critical Heat Flux (CHF) has been performed. This review covers most of the flow geometries such as tubes, concentric and eccentric annuli, rectangular channels, irregular-shaped channels and bundles. The following geometric parameters have been found to strongly influence the CHF: (i) hydraulic-equivalent diameter, (ii) heated-equivalent diameter, (iii) gap size, (iv) unheated adjacent surface, (v) heated adjacent surface, (vi) curvature, (vii) eccentricity (including bowing), and (viii) channel shape. It is found that some of the geometric effects on CHF depend on the flow conditions and the CHF type. For each geometry the parametric trends have been described, whenever sufficient experimental results are available. A review and assessment of the available prediction methods is conducted. The following trends have been identified in this study: (i) in general the CHF in annuli (concentric and eccentric) is lower than that in tubes, especially for high quality and narrow gaps; (ii) for rectangular channels and irregular-shaped channels, corners can cause a large CHF reduction; (iii) the CHF for concave surface is significantly higher than the CHF for a convex surface; (iv) the effect of gap size in concentric annuli is different for a departure from nucleate boiling (DNB) type CHF and CHF type for the annular flow regime. For the first CHF type reduction in gap size results in a CHF decrease, while for the second CHF type it results in CHF enhancement; and (v) heating the adjacent surface results in a CHF increase. Based on the observed trends, CHF correction factors have been derived for each geometry. Finally, an interim CHF prediction method for subchannels and flow conditions of interest to CANDU$\sp*$ reactors has been proposed. ftn$\sp*$CANDU--CANada Deuterium Uranium, a registered trademark.
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Le, Clech Pierre. "Process configurations and fouling in membrane bioreactors." Thesis, Cranfield University, 2002. http://dspace.lib.cranfield.ac.uk/handle/1826/11336.

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MBR process consists of a suspended growth biological reactor combined with a membrane unit. The widespread of this system for waste water treatment is contained by membrane fouling, which is strongly influenced by three factors: biomass characteristics, operating conditions and membrane characteristics. Fouling control techniques mainly include low-flux operation (sub-critical flux operation) and/or high-shear slug flow aeration in submerged. configuration. Based on the concept of the critical flux (Jo), the flux-step method has been developed to more fully characterise transmembrane pressure (TMP) behaviour during constant-fluxoperation. A zero rate of TMP increase was never attained during the trial, such that no critical flux, in its strictest definition, could be defined in this study for a submerged MBRs challenged with real and simulant sewage. Under similar operating conditions, Jc was obtained around 18 and 10 L.m-2.h-1 for a submerged MBR fed by real and synthetic sewage respectively. Three TMP-based parameters have been defined, all indicating the same flux value at which fouling starts to be more significant (the weak form of Jo). Results from factorial experimental designs revealed the relative effect of MLSS levels, aeration rate and membrane pore size on J, The MLSS effect on Jc was generally around double that of the aeration effect. The calculation of mean sub-critical values for the different TMP-based parameters suggest lower short-term fouling resistance for large pore sized membranes. A direct comparison between the two MBR configurations revealed a greater J, for the submerged compared to the SS MBR (22 and 11 L.m-2.h-1 respectively) under similar hydraulic conditions. The fluid hydrodynamics has been studied for both configurations, leading to an accurate calculation of shear at the membrane surface in SS MBR and to the determination of the minimum gas velocity required for Taylor bubble formation in submerged MBR (around 0.1 m.s-1). Finally, the effect of operating conditions such as process configuration, feed nature, and aeration type on biomass characteristics has been assessed and link to membrane fouling. Key words: Fouling, MBR, critical flux, process configuration, biomass characterisation.
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Truong, Bao H. (Bao Hoai). "Determination of pool boiling Critical Heat Flux enhancement in nanofluids." Thesis, Massachusetts Institute of Technology, 2007. http://hdl.handle.net/1721.1/41689.

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Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, June 2007.
"May 2007."
Includes bibliographical references (leaves 51-53).
Nanofluids are engineered colloids composed of nano-size particles dispersed in common fluids such as water or refrigerants. Using an electrically controlled wire heater, pool boiling Critical Heat Flux (CHF) of Alumina and Silica water-based nanofluids of concentration less than or equal to 0.1 percent by volume were measured. Silica nanofluids showed CHF enhancement up to 68% and there seems to be a monotonic relationship between nanoparticle concentration and magnitude of enhancement. Alumina nanofluids had CHF enhancement up to 56% but the peak occurred at the intermediate concentration. The boiling curves in nanofluid were found to shift to the left of that of water and correspond to higher nucleate boiling heat transfer coefficients in the two-phase flow regime. SEM images show a porous coating layer of nanoparticles on wires subjected to nanofluid CHF tests. These coating layers change the morphology of the heater's surface, and are responsible for the CHF enhancement. The thickness of the coating was estimated using SEM and was found ranging from 3.0 to 6.0 micrometers for Alumina, and 3.0 to 15.0 micrometers for Silica. Inductively Coupled Plasma Spectroscopy (ICP-OES) analyses were also attempted to quantify the mass of the particle deposition but the results were inconsistent with the estimates from the SEM measurement.
by Bao H. Truong.
S.B.
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Chen, Geng. "Analytical and experimental studies of critical heat flux in complex geometry." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 2001. http://www.collectionscanada.ca/obj/s4/f2/dsk3/ftp05/NQ66137.pdf.

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Lalonde, Richard. "Flux line interactions in conventional and high critical transition temperature superconductors." Thesis, University of Ottawa (Canada), 1990. http://hdl.handle.net/10393/6031.

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We have developed a novel experimental approach for the study of the interaction of sheets of non parallel flux lines in hysteric type II superconductors. We continuously monitor the evolution of the components of the magnetic flux density $\Vert$ and $\perp$ to $H\sb{a}$ (i.e. $\langle B\sb{z}\rangle$ and $\langle B\sb{y}\rangle$) as $H\sb{a}$ is raised to various intensities, and then reduced to zero. In our investigation of a high $T\sb{c}(YBa\sb{2}Cu\sb{3}O\sb{7-x}$) ceramic, $H\sb{a}$ exceeded $H\sb{*}$, the first full penetration field. We applied the phenomenological Clem general critical state model to the analysis of our extensive observations. A computer program was developed to solve the four coupled differential equations of this theory with appropriate physical constraints for the situations prevailing in our experiment. This analysis provides detailed insight into the evolution of the intricate configurations of the magnetic flux density $\vec B$(x), the critical current density, $\vec J$(x), and electric field $\vec E$(x) patterns as the injected and trapped flux lines are made to interact, unpin, migrate and undergo flux cutting processes. The model is seen to generate the variety of complicated measured curves of $\langle B\sb{y}\rangle$ and $\langle B\sb{z}\rangle$ vs $H\sb{a}$ very satisfactorily. (Abstract shortened by UMI.)
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Tanase, Aurelian. "Improved methodology for deriving the critical heat flux look-up table." Thesis, University of Ottawa (Canada), 2007. http://hdl.handle.net/10393/27923.

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A literature review on critical heat flux (CHF) prediction methods confirmed that the CHF look-up table (LUT) has many advantages over the other prediction methods: it covers the widest range of flow conditions, it is the most accurate CHF prediction method and it is computationally very efficient. The LUT has been included in the major thermalhydraulics and safety analysis computer codes. The LUT accuracy has increased over the years, although several areas have been identified where further improvements are desirable. These areas include (i) the screening of the experimental data, (ii) effect of the heated channel diameter and length on the CHF, and (iii) difficulties in predicting the CHF in the limiting quality region in LUT, at low flow/low pressure conditions and in the very high dryout quality range. This thesis describes the various improvements that have been made to the LUT derivation. In addition to the improvements in the LUT derivation methodology, a new visual analysis technique that allows simultaneous LUT trend visualization and comparison in all parametric directions has been developed. Based on the findings and improvements in the LUT derivation methodology, a new version of the LUT has been developed. The error analysis revealed that refined data screening and removal of outliers is an effective method for improving the CHF LUT accuracy. Because the majority of the experimental data were obtained for diameters close to the standard 8 mm ID, a better correction of diameter effect on the CHF does not significantly affect the overall LUT accuracy, although it appears to be very important at specific conditions such as low flow or extreme diameters.
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Roach, Gregory M. Jr. "Onset of flow instability and critical heat flux in uniformly-heated microchannels." Thesis, Georgia Institute of Technology, 1998. http://hdl.handle.net/1853/19048.

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Books on the topic "Critical flux"

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Centre, Bhabha Atomic Research. Flux mapping system for AHWR critical facility. Mumbai: Bhabha Atomic Research Centre, 2007.

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Saha, Sujoy Kumar, and Gian Piero Celata. Critical Heat Flux in Flow Boiling in Microchannels. Cham: Springer International Publishing, 2015. http://dx.doi.org/10.1007/978-3-319-17735-9.

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Cheung, F. B. Critical heat flux (CHF) phenomenon on a downward facing curved surface: Effects of thermal insulation. Washington, DC: Division of Systems Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1998.

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Tain, Ra-Min. Assessment of critical heat flux correlations for high steam quality condition. Lung-Tan, Republic of China: Institute of Nuclear Energy Research, 1987.

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Sjöberg, Anders. Assessment of RELAP5/MOD 2 against 25 dryout experiments conducted at the Royal Institute of Technology. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986.

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W, Weber Harald, ed. Proceedings of the 7th International Workshop on Critical Currents in Superconductors: Alpbach, Austria, 24-27 Jan. 1994. Singapore: World Scientific, 1994.

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Sjöberg, Anders. Assessment of RELAP5/MOD 2 against 25 dryout experiments conducted at the Royal Institute of Technology. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986.

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Sjöberg, Anders. Assessment of RELAP5/MOD 2 against 25 dryout experiments conducted at the Royal Institute of Technology. Washington, DC: Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986.

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W, Collings E., Weber Harald W, and Zhou L, eds. Critical currents in superconductors for practical applications: Proceedings of the International Workshop : Xi'an, March 6-8, 1997. Singapore: World Scientific, 1998.

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Sorrell, Charles A. Aluminum fluxing salts: A critical review of the chemistry and structure of alkali aluminum halides. [Pittsburgh, Pa.]: U.S. Dept. of the Interior, Bureau of Mines, 1986.

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Book chapters on the topic "Critical flux"

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Li, Xianhui, and Jianxin Li. "Critical Flux." In Encyclopedia of Membranes, 475–77. Berlin, Heidelberg: Springer Berlin Heidelberg, 2016. http://dx.doi.org/10.1007/978-3-662-44324-8_2193.

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Li, Xianhui, and Jianxin Li. "Critical Flux." In Encyclopedia of Membranes, 1–3. Berlin, Heidelberg: Springer Berlin Heidelberg, 2015. http://dx.doi.org/10.1007/978-3-642-40872-4_2193-1.

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Saha, Sujoy Kumar, and Gian Piero Celata. "Critical Heat Flux." In Critical Heat Flux in Flow Boiling in Microchannels, 13–51. Cham: Springer International Publishing, 2015. http://dx.doi.org/10.1007/978-3-319-17735-9_2.

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Matsushita, Teruo. "Measurement Methods for Critical Current Density." In Flux Pinning in Superconductors, 189–209. Berlin, Heidelberg: Springer Berlin Heidelberg, 2014. http://dx.doi.org/10.1007/978-3-642-45312-0_5.

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Kanizawa, Fabio Toshio, and Gherhardt Ribatski. "Critical Heat Flux and Dryout." In Mechanical Engineering Series, 217–40. Cham: Springer International Publishing, 2021. http://dx.doi.org/10.1007/978-3-030-68704-5_6.

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Dascal, Marcelo. "Identities in Flux: Arabs and Jews in Israel." In Critical Discourse Analysis, 150–66. London: Palgrave Macmillan UK, 2003. http://dx.doi.org/10.1057/9780230514560_8.

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Dascal, Marcelo. "Identities in Flux: Arabs and Jews in Israel." In Critical Discourse Analysis, 150–66. London: Palgrave Macmillan UK, 2003. http://dx.doi.org/10.1057/9780230288423_8.

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Gamble, J. "Fluid Flux Across the Microvascular Endothelium." In Current Concepts in Critical Care, 3–19. London: Springer London, 1988. http://dx.doi.org/10.1007/978-1-4471-1443-7_1.

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Surjanto, Williams, and Charles Lim. "Finding Fast Flux Traffic in DNS Haystack." In Critical Information Infrastructures Security, 69–82. Cham: Springer International Publishing, 2020. http://dx.doi.org/10.1007/978-3-030-58295-1_6.

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Akimoto, Hajime, Yoshinari Anoda, Kazuyuki Takase, Hiroyuki Yoshida, and Hidesada Tamai. "Boiling Heat Transfer and Critical Heat Flux." In An Advanced Course in Nuclear Engineering, 315–46. Tokyo: Springer Japan, 2016. http://dx.doi.org/10.1007/978-4-431-55603-9_16.

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Conference papers on the topic "Critical flux"

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Katto, Yoshiro. "CRITICAL HEAT FLUX IN BOILING." In International Heat Transfer Conference 8. Connecticut: Begellhouse, 1986. http://dx.doi.org/10.1615/ihtc8.2390.

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Shim, W. Jaewoo, Joo-Yong Park, Ji-Su Lee, and Dong Kook Kim. "Critical Heat Flux in Tubes With Cosine Axial Heat Flux." In ASME 2005 Summer Heat Transfer Conference collocated with the ASME 2005 Pacific Rim Technical Conference and Exhibition on Integration and Packaging of MEMS, NEMS, and Electronic Systems. ASMEDC, 2005. http://dx.doi.org/10.1115/ht2005-72504.

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In this study a method to predict CHF (Critical Heat Flux) in vertical round tubes with cosine heat flux distribution was examined. For this purpose a uniform correlation, based on local condition hypothesis, was developed from 9,366 CHF data points of uniform heat flux heaters. The CHF data points used were collected from 13 different sources had the following parameter ranges: 1.01 ≤ P (pressure) ≤ 206.79 bar, 9.92 ≤ G (mass flux) ≤ 18,619.39 kg/m2s, 0.00102 ≤ D (diameter) ≤ 0.04468 m, 0.0254 ≤ L (length) ≤ 4.966 m, 0.11 ≤ qc (CHF) ≤ 21.42 MW/m2, and −0.87 ≤ X (exit qualities) ≤ 1.58. The result of this work showed that the uniform CHF correlation could be used to predict CHF accurately in a non-uniform heat flux heater for wide flow conditions. Furthermore, the location, where CHF occurs in non-uniform heat flux distribution, can also be determined accurately with the local variables: the system pressure (P), tube diameter (D), mass flux of water (G), and true mass flux of vapor (GXt). The new correlation predicted CHF with cosine heat flux, 297 data points from 5 different published sources, within the root mean square error of 12.42% and average error of 1.06% using the heat balance method.
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Golubovic, Mihajlo, H. D. Madhawa Hettiarachchi, and William M. Worek. "Nano Fluids and Critical Heat Flux." In ASME 2008 First International Conference on Micro/Nanoscale Heat Transfer. ASMEDC, 2008. http://dx.doi.org/10.1115/mnht2008-52360.

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In recent years nanofluids have been attracting significant attention in the heat transfer research community. These fluids are obtained by suspending nanoparticles having sizes between 1 and 100 nm in regular fluids. It was found by several researchers that the thermal conductivity of these fluids can be significantly increased when compared to the same fluids without nanoparticles. Also, it was found that pool boiling critical heat flux increases in nanofluids. In this paper, our objective is to evaluate the impact of different nanoparticle characteristics including particle concentration, size and type on critical heat flux experimentally at saturated conditions. As result, this work will document our experimental findings about pool boiling critical heat flux in different nanofluids. In addition, we will identify reasons behind the increase in the critical heat flux and present possible approaches for analytical modeling of critical heat flux in nanofluids at saturated conditions.
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Chow, Louis, Maninder Sehmbey, and Martin Pais. "Critical heat flux in spray cooling." In 34th Aerospace Sciences Meeting and Exhibit. Reston, Virigina: American Institute of Aeronautics and Astronautics, 1996. http://dx.doi.org/10.2514/6.1996-727.

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Celata, Gian Piero, Maurizio Cumo, Francesco D'Annibale, G. E. Farello, and T. Setaro. "CRITICAL HEAT FLUX IN FLOW TRANSIENTS." In International Heat Transfer Conference 8. Connecticut: Begellhouse, 1986. http://dx.doi.org/10.1615/ihtc8.3260.

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TILTON, DONALD, LOUIS CHOW, E. MAHEFKEY, and GARY SWITZER. "Critical heat flux phenomena in spray cooling." In 5th Joint Thermophysics and Heat Transfer Conference. Reston, Virigina: American Institute of Aeronautics and Astronautics, 1990. http://dx.doi.org/10.2514/6.1990-1729.

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Nishiguchi, Shotaro, Naoki Ono, and Masahiro Shoji. "Critical Heat Flux of Butanol Aqueous Solution." In ASME 2008 6th International Conference on Nanochannels, Microchannels, and Minichannels. ASMEDC, 2008. http://dx.doi.org/10.1115/icnmm2008-62378.

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Aqueous solutions of some alcohols such as butanol show peculiar temperature dependence of surface tension. Contrary to ordinary liquids or solutions, the surface tension increases with temperature at the range of high liquid temperature. So at the triple-phase point on a heated surface, the thermo-capillary force acts for the liquid to wet the heated surface, so the solutions are sometimes called as “self-wetting liquids”. Self-wetting liquids may prohibit the dry-out of a heated surface so that the heat transfer performance would be enhanced. For this reason, applications of self-wetting liquids to heat transfer devices such as heat pipes are actively studied in recent years. However, the heat transfer characteristics of boiling of self-wetting liquids are not fully understood. In the present research, a boiling experiment of butanol aqueous solution was performed on a heated fine wire in order to make clear the fundamental heat transfer characteristics. A heated wire configuration is easy to observe the phenomena and easy to address the fundamental issues of boiling. In the present experiment, nucleate boiling heat transfer were investigated with special attention to critical heat flux (CHF), by changing solution concentration and temperature. Bubbling aspects were observed by high-speed video camera. It is found from the experiment that CHF is generally enhanced 20 to 50% when compared to the case of pure water. It is also found that at a certain concentration and at a certain liquid temperature, peculiar boiling takes place where very small bubbles are emitted from the heated wire and CHF enhancement becomes very large from 2 to 3 times higher than CHF of pure water. The temperature when the peculiar boiling takes place is close to boiling temperature of the solution. These results suggest the possibility of application of aqueous solution to high-performance cooling devices utilizing micro-scaled channels because generating bubbles are small enough so that the pressure loss of the flow passage is small and heat transfer rate is very large.
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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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Umekawa, Hisashi, Mamoru Ozawa, and Takeshi Sanami. "Restriction of Critical Heat Flux by Critical Flow Condition in Capillary Tube." In ASME 2003 1st International Conference on Microchannels and Minichannels. ASMEDC, 2003. http://dx.doi.org/10.1115/icmm2003-1073.

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Critical heat flux (CHF) is a very important design factor of boiling channel, then, so many investigations have been conducted so far. In the case of small diameter channel, the main interest is related with the heat removal of high heat flux component. Therefore, CHF of that system should be predicted by DNB condition. On the other hand, CHF under low heat flux condition in small channel can be considered as the relation with two kinds of restrictions. In this investigation, the confirmation of the relationship of two restrictions in CHF was principal purpose. The CHF of this system was basically decided by the dryout condition, but it deviated from the dryout under certain conditions. In those conditions, the critical flow condition achieved in lower heat flux compared with that of the dryout. Owing to this restriction of the flow rate by critical flow condition, pseudo CHF condition occurs. Experimental results have expressed these relationships between CHF and critical flow condition well.
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Wu, Zan, and Wei Li. "Correlations for Saturated Critical Heat Flux in Microchannels." In 2010 14th International Heat Transfer Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/ihtc14-22533.

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Experimental results of the saturated-flow boiling critical heat flux (CHF) in microchannels for both multi- and single-channel configurations were obtained from the literature. The collected database contains 629 data points, covering 5 refrigerants, nitrogen, and water, for a wide range of operational conditions, and different micro-channel dimensions. The whole database was analyzed by using four empirical correlations to verify their respective accuracies. However, none of the existing correlations could predict the entire database precisely. A saturated CHF correlation was proposed by using boiling number, length-to-diameter ratio, and exit quality. The new correlation can predict the overall micro-channel database accurately on the whole. It predicts almost 97.0% of the non-aqueous data (except R12 data points located in the macro-scale region) and 94.0% of the water data within the ± 30% error band.
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Reports on the topic "Critical flux"

1

Jafri, T., T. J. Dougherty, and B. W. Yang. Correlation of critical heat flux data for uniform tubes. Office of Scientific and Technical Information (OSTI), September 1995. http://dx.doi.org/10.2172/111456.

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Shumway, R. New critical heat flux method for RELAP5/MOD3: Completion report. Office of Scientific and Technical Information (OSTI), January 1989. http://dx.doi.org/10.2172/6044085.

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Cheung, F. B., K. H. Haddad, and Y. C. Liu. Critical heat flux (CHF) phenomenon on a downward facing curved surface. Office of Scientific and Technical Information (OSTI), June 1997. http://dx.doi.org/10.2172/491560.

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Rao, D. V., and M. S. El-Genk. Critical heat flux predictions for the Sandia Annular Core Research Reactor. Office of Scientific and Technical Information (OSTI), August 1994. http://dx.doi.org/10.2172/10196536.

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Kim, Sung J., and Jungho Kim. Surface De-Wetting Based Critical Heat Flux Model Development and Validation. Fort Belvoir, VA: Defense Technical Information Center, February 2013. http://dx.doi.org/10.21236/ada578387.

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Scharmer, K., and H. G. Eckert. FOEHN: The critical experiment for the Franco-German High Flux Reactor. Office of Scientific and Technical Information (OSTI), January 1991. http://dx.doi.org/10.2172/7399183.

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Ling, X. S., J. I. Budnick, and D. Shi. Flux motion in the self-organized critical state of type-II superconductors. Office of Scientific and Technical Information (OSTI), April 1991. http://dx.doi.org/10.2172/10144502.

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Shadday, M. A. Jr. Critical heat flux concerns during the flow instability phase of a DEGB LOCA. Office of Scientific and Technical Information (OSTI), August 1990. http://dx.doi.org/10.2172/5037231.

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Shadday, M. A. Jr. Critical heat flux concerns during the flow instability phase of a DEGB LOCA. Office of Scientific and Technical Information (OSTI), August 1990. http://dx.doi.org/10.2172/10155739.

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10

Kirillov, P. L., and I. P. Smogalev. On the look-up tables for the critical heat flux in tubes (history and problems). Office of Scientific and Technical Information (OSTI), September 1995. http://dx.doi.org/10.2172/111418.

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