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Relevant bibliographies by topics / Dittus-boelter

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Academic literature on the topic 'Dittus-boelter'

Author: Grafiati

Published: 4 June 2021

Last updated: 9 February 2022

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Journal articles on the topic "Dittus-boelter"

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Winterton, R. H. S. "Where did the Dittus and Boelter equation come from?" International Journal of Heat and Mass Transfer 41, no. 4-5 (1998): 809–10. http://dx.doi.org/10.1016/s0017-9310(97)00177-4.

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Kumar, Rajneesh, Anoop Kumar, and Varun Varun. "Computational fluid dynamics based study for analyzing heat transfer and friction factor in semi-circular rib-roughened equilateral triangular duct." International Journal of Numerical Methods for Heat & Fluid Flow 27, no. 4 (2017): 941–57. http://dx.doi.org/10.1108/hff-10-2015-0438.

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Purpose The purpose of this computational fluid dynamics (CFD)-based study on semicircular rib-roughened equilateral triangular duct is to investigate heat transfer, friction factor and thermohydraulic performance parameter. The analysis is carried out by simulating problem in ANSYS (Fluent). The Reynolds number in the study varies from 4,000 to 24,000. Nusselt number is calculated for different Reynolds number using various turbulent models available in ANSYS (Fluent) for a smooth duct and compared the results with the Dittus–Boelter correlation. Design/methodology/approach The analysis has b

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Cieśliński, Janusz T., Artur Fiuk, Krzysztof Typiński, and Bartłomiej Siemieńczuk. "Heat transfer in plate heat exchanger channels: Experimental validation of selected correlation equations." Archives of Thermodynamics 37, no. 3 (2016): 19–29. http://dx.doi.org/10.1515/aoter-2016-0017.

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Abstract This study is focused on experimental investigation of selected type of brazed plate heat exchanger (PHEx). The Wilson plot approach was applied in order to estimate heat transfer coefficients for the PHEx passages. The main aim of the paper was to experimentally check ability of several correlations published in the literature to predict heat transfer coefficients by comparison experimentally obtained data with appropriate predictions. The results obtained revealed that Hausen and Dittus-Boelter correlations underestimated heat transfer coefficient for the tested PHEx by an order of

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Men, Qiming, Xuesheng Wang, Xiang Zhou, and Xiangyu Meng. "Heat Transfer Analysis of Passive Residual Heat Removal Heat Exchanger under Natural Convection Condition in Tank." Science and Technology of Nuclear Installations 2014 (2014): 1–8. http://dx.doi.org/10.1155/2014/279791.

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Aiming at the heat transfer calculation of the Passive Residual Heat Removal Heat Exchanger (PRHR HX), experiments on the heat transfer of C-shaped tube immerged in a water tank were performed. Comparisons of different correlation in literatures with the experimental data were carried out. It can be concluded that the Dittus-Boelter correlation provides a best-estimate fit with the experimental results. The average error is about 0.35%. For the tube outside, the McAdams correlations for both horizontal and vertical regions are best-estimated. The average errors are about 0.55% for horizontal r

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Karlsson, T. "Numerical Evaluation of Plate Heat Exchanger Performance in Geothermal District Heating Systems." Proceedings of the Institution of Mechanical Engineers, Part A: Journal of Power and Energy 210, no. 2 (1996): 139–47. http://dx.doi.org/10.1243/pime_proc_1996_210_021_02.

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This paper describes the performance of plate heat exchangers in residential water radiator heating systems receiving their heat from geothermal resources. Radiator theory is reviewed and determination of annual hot water requirements for space heating is discussed. Performance evaluation is made of plate heat exchangers and results obtained by means of two equations commonly used for this purpose, the Sieder–Tate and the Dittus–Boelter equations, compared to results obtained with a simplified equation where heat transfer in the heat exchanger is assumed to depend only on the fluid mass flow o

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Mohammed, Mohammed K., M. Kh Abdolbaqi, Thamir K. Ibrahim, Rizalman Bin Mamat, and Omar I. Awad. "Experimental and Numerical investigation of Heat transfer enhancement using Al2O3-Ethylene Glycol/Water nanofluids in straight channel." MATEC Web of Conferences 225 (2018): 01019. http://dx.doi.org/10.1051/matecconf/201822501019.

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A study of computational fluid dynamics has been conducted to study the characteristics of the heat transfer and friction factor of Al2O3/Ethylene glycol-water nanofluid flowing in straight channel. The three dimensional realizable k-e turbulent model with enhanced wall treatment was utilized. As well as were used Temperature dependent thermophysical properties of nanofluid and water. The evaluation of the overall performance of the tested channel was predicated on the thermohydrodynamic performance index. The obtained results showed that the difference in behaviour depending on the parameter

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Williams, Wesley C. "If the Dittus and Boelter equation is really the McAdams equation, then should not the McAdams equation really be the Koo equation?" International Journal of Heat and Mass Transfer 54, no. 7-8 (2011): 1682–83. http://dx.doi.org/10.1016/j.ijheatmasstransfer.2010.11.047.

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Chin, D., J. C. Hermanson, and L. J. Spadaccini. "Thermal Stability and Heat Transfer Characteristics of Methane and Natural Gas Fuels." Journal of Engineering for Gas Turbines and Power 117, no. 3 (1995): 462–67. http://dx.doi.org/10.1115/1.2814118.

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The thermal decomposition and heat transfer characteristics of gaseous, high-purity methane, several methane–hydrocarbon mixtures, and a typical natural gas fuel were evaluated using an electrically heated, stainless-steel tube test apparatus. Of several candidate heat transfer correlations, the Dittus–Boelter heat transfer correlation provided the best fit of the methane heat transfer data over the range of Reynolds numbers 10,000 to 215,000. The thermal stability (i.e., deposit formation) characteristics of the methane–hydrocarbon mixtures and the natural gas fuel were established and compar

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Chang, Shyy, Wei-Ling Cai, and Ruei-Jhe Wu. "Heat Transfer Enhancement by Detached S-Ribs for Twin-Pass Parallelogram Channel." Inventions 3, no. 3 (2018): 50. http://dx.doi.org/10.3390/inventions3030050.

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Detached S-ribs are proposed to arrange in the stagger manner along two parallelogram straight channels interconnecting with a 180° smooth-walled sharp bend for heat transfer enhancements. The detailed Nusselt number distributions over the two opposite channel endwalls at Reynolds numbers of 5000, 7500, 10,000, 12,500, 15,000 and 20,000 are measured using the steady-state infrared thermography method. The accompanying Fanning friction factors are evaluated from the measured pressure drops across the entire test channel. Having acquired the averaged heat transfer properties and Fanning friction

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Şenay, Gülbanu, Metin Kaya, Engin Gedik, and Muhammet Kayfeci. "Numerical investigation on turbulent convective heat transfer of nanofluid flow in a square cross-sectioned duct." International Journal of Numerical Methods for Heat & Fluid Flow 29, no. 4 (2019): 1432–47. http://dx.doi.org/10.1108/hff-06-2018-0260.

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Purpose The purpose of this study is to numerically investigate the heat transfer enhancement by using two different nanofluids flow throughout the square duct under a constant heat flux (500 × 103 W/m2). Design/methodology/approach In numerical computations, ANSYS Fluent code based on the finite volume method was used to solve governing equations by iteratively. Water, Al2O3-water and TiO2-water nanofluids were used for different flow velocities changing 1 m/s to 8 m/s (i.e. Reynolds number varying from 3,000 to 100,000). Findings The results were compared with results published previously in

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Dissertations / Theses on the topic "Dittus-boelter"

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Mårtenson, Adam. "Modernisering och utveckling av befintligt beräkningsprogram för prestandauppföljning av ånggeneratorer." Thesis, Uppsala universitet, Elektricitetslära, 2019. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-377997.

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This thesis is centered around the computional program PASGO. PASGO is used for calculations for making performance monitoring of the steam generators in Ringhals reactor 3 and 4, especially concerning fouling of the steam generator tubes. The main goal of this thesis project was to convert the program code from the programming language Turbo Pascal 6.0 into a more modern language that works with the current Windows operative systems. Apart from a straight conversion of the code, a function to make automatic input from an Excel-file to the program was also requested. The thesis also includes a

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Conference papers on the topic "Dittus-boelter"

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Spore, Jay, and Glenn Roth. "Heat Transfer for Supercritical Flow With TRACE." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16753.

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Abstract Flow regimes at water pressures above the critical pressure are characterized as supercritical flow. Supercritical flows have no phase change. The heat transfer from the wall to the fluid is single phase (there is no boiling or condensation). Experimental data indicate that for conditions that involve supercritical single-phase heat transfer, the Dittus-Boelter heat transfer correlation can be in significant error. A pseudo-critical temperature can be defined as a function of pressure for pressures that exceed the supercritical pressure. The pseudo-critical temperature is defined for

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Johns, Jesse M., and W. D. Reece. "A New Approach to Calculating Fuel Temperature in TRIGA Mark I Research Reactors." In 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/icone20-power2012-54921.

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Often a forced convection heat transfer coefficient is used to calculate the peak fuel temperature for a rectangular lattice TRIGA core even though the core is cooled by natural convection. The arguments for applying a forced convection empirical relationship are examined and another relationship is suggested. The peak fuel temperature was calculated using two different correlations, Dittus-Boelter and natural convection, for pool temperatures of 30°C and 60°C. The Dittus-Boelter correlation predicted a fuel temperature rise of 1.85°C for this difference in pool temperature, contrary to the pr

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Gospodinov, Yevgeniy, Sarah Mokry, Pavel Kirillov, and Igor Pioro. "Supercritical Water Heat Transfer in a Vertical Bare Tube." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48546.

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This paper presents selected results on heat transfer to supercritical water flowing upward in a 4-m-long vertical bare tube. Supercritical water heat-transfer data were obtained at pressures of about 24 MPa, mass fluxes of 200 – 1500 kg/m2s, heat fluxes up to 884 kW/m2 and inlet temperatures from 320 to 350°C for several combinations of wall and bulk-fluid temperatures that were below, at or above the pseudocritical temperature. In general, the experiments confirmed that there are three heat-transfer regimes for forced convective heat transfer to water flowing inside tubes at supercritical pr

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Wang, Mei, Yan Wen, Suizheng Qiu, Guanghui Su, and Weifeng Ni. "Experimental Study on Thermal-Hydraulic Performance of Single-Phase Water Flow in Narrow Rectangular Channel." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-75848.

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The purpose of this study is to discover the differences of pressure drop and heat transfer of single-phase water flow between conventional channels and narrow rectangular channels. Furthermore, the differences between the level and the vertical channel have been studied. The gap of the test channel is 1.8mm. Compared with conventional channels, the narrow rectangular channel showed differences in both flow and heat transfer characteristics. The critical Reynolds number of transition from laminar flow to turbulent flow is 900∼1300, which is smaller compared with conventional channels. The fric

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Yang, Zhendong, Qincheng Bi, Han Wang, Gang Wu, and Laurence K. H. Leung. "Assessment of Heat-Transfer Correlations Against Experimental Data Obtained With Supercritical Water in Vertical Annuli." In 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. American Society of Mechanical Engineers, 2012. http://dx.doi.org/10.1115/icone20-power2012-54206.

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Eleven correlations proposed for supercritical heat-transfer coefficients were assessed against a set of experimental data obtained recently with supercritical water flow in a vertical annular test section at Xi’an Jiaotong University. The inner heated rod of the test section had an outer diameter of 8 mm, while the outer unheated tube had an inner diameter of 16 mm (resulting in a gap size of 4 mm). The experiment covered pressure range from 23 to 28 MPa, mass-flux range from 350 to 1000 kg/m2s, and heat-flux range from 200 to 1000 kW/m2. The assessment shows relatively good agreement between

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Mokry, Sarah, Yevgeniy Gospodinov, Igor Pioro, and Pavel Kirillov. "Supercritical Water Heat-Transfer Correlation for Vertical Bare Tubes." In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-76010.

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This paper presents an analysis of heat transfer to supercritical water in bare vertical tubes. A large set of experimental data, obtained in Russia, was analyzed and an updated heat-transfer correlation for supercritical water was developed. This experimental dataset was obtained within conditions similar to those for proposed SuperCritical Water-cooled nuclear Reactor (SCWR) concepts. Thus, the new correlation presented in this paper can be used for preliminary heat-transfer calculations in SCWR fuel channels. The experimental dataset was obtained for supercritical water flowing upward in a

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Mokry, Sarah, and Igor Pioro. "Improvement of Supercritical Water Heat-Transfer Correlations for Vertical Bare Tubes." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30137.

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Currently, there are a number of Generation IV SuperCritical Water-cooled nuclear Reactor (SCWR) concepts under development worldwide. These high temperature, high pressure reactors will have much higher operating parameters compared to current Nuclear Power Plants (NPPs) (i.e., steam pressures of about 25 MPa and steam outlet temperatures up to 625°C). Additionally, SCWRs will have a simplified flow circuit in which steam generators, steam dryers, steam separators, etc. will be eliminated. In support of developing these SCWRs, studies are currently being conducted for heat transfer at supercr

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Ke, Zhaoqing, Jian Pu, Jianhua Wang, Lei Wang, Zhiqiang Zhang, and Xiangyu Wu. "Investigations on Fluid Flow and Heat Transfer Performances Within a Real Turbine Blade Channel." In ASME Turbo Expo 2014: Turbine Technical Conference and Exposition. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/gt2014-25097.

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The characteristics of fluid flow and heat transfer within a smooth three-pass channel of a real low pressure (LP) turbine blade have been investigated through experimental and numerical approaches. The serpentine channel consists of two inlet passes, two dividing walls, two 180 degree bends, twenty-five exits at the trailing edge, and two exits at the blade tip. In the experiments, purified water was used as working medium, the secondary flow patterns at five cross-sections were captured by a particle image velocimetry (PIV) system, the inlet Reynolds number was controlled by a turbine flow m

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Mokry, Sarah, and Igor Pioro. "Investigation of Characteristic-Temperature Approaches for Heat-Transfer Correlations at Supercritical Conditions." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16765.

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It is expected that the next generation of water-cooled nuclear reactors will operate at supercritical pressures (∼25 MPa) and high coolant temperatures (350–625°C). In support of the development of SuperCritical Water-cooled Reactors (SCWRs), research is currently being conducted for heat-transfer at supercritical conditions. Currently, there are no experimental datasets for heat transfer from power reactor fuel bundles to the fuel coolant (water) available in open literature. Therefore, for preliminary calculations, heat-transfer correlations obtained with bare-tube data can be used as a con

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Wieselquist, William A. "One Validation Case of the CFD Software Fluent: Part of the Development Effort of a New Reactor Analysis Tool." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22694.

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To model Generation IV reactor systems in detail, INEEL is currently developing a new thermal hydraulic analysis tool coupling RELAP5-3D / ATHENA© and the computational fluid dynamics (CFD) software, Fluent. One of the first steps in this endeavor is extensive validation and verification (V&V) of Fluent for various situations of interest, such as the abrupt expansion of a gas entering a gas-cooled reactor core. Fluent results were compared to validation data provided by Baughn, et al. on turbulent air flow through an axisymmetric pipe expansion with constant wall heat flux [1] and uniform

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