Assessment of Look-up tables for the prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water
1
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
The evaluation of available Look-Up Tables for prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water with the aim of their further use in computational analyses of various Fuel Assembles of Supercritical Water-Cooled Reactors is made. The comparison between the calculations based on Look-Up Tables with the values from empirical correlations and experimental data for smooth and wire-wrapped rod bundles was presented. The obtained results showed that Look-Up Table of the University of Ottawa, which was created to describe improved and deteriorated heat transfer regimes in round tubes, allows describing available data points with 30 % of the mean square deviation. It is noted that the presence of wire intensifies heat transfer exchange near pseudocritical temperature region but existing versions of Look-Up Tables cannot take into account this effect. Nevertheless, there is potential for further improvement in predicting the heat transfer coefficient using Look-Up Table by introducing additional correction factors.
Abstract
The evaluation of available Look-Up Tables for prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water with the aim of their further use in computational analyses of various Fuel Assembles of Supercritical Water-Cooled Reactors is made. The comparison between the calculations based on Look-Up Tables with the values from empirical correlations and experimental data for smooth and wire-wrapped rod bundles was presented. The obtained results showed that Look-Up Table of the University of Ottawa, which was created to describe improved and deteriorated heat transfer regimes in round tubes, allows describing available data points with 30 % of the mean square deviation. It is noted that the presence of wire intensifies heat transfer exchange near pseudocritical temperature region but existing versions of Look-Up Tables cannot take into account this effect. Nevertheless, there is potential for further improvement in predicting the heat transfer coefficient using Look-Up Table by introducing additional correction factors.
참고문헌 (33)
- Y. Oka, "Super Light Water Reactors and Super Fast Reactors: Supercritical-Pressure Light Water Cooled Reactors" (2010), Springer US
- The Generation IV International Forum, "A Technology Roadmap for Generation IV Nuclear Energy Systems", ~ (2002)
- "Technology roadmap update for generation IV nuclear energy systems, Gen IV International Forum" (2014)[URL]
- I. H. Bell, "Pure and pseudo-pure fluid thermophysical property evaluation and the open-source thermophysical property library CoolProp", Industrial& Engineering Chemistry Research, 53, pp.2498~2508 (2014)[DOI]
- D. C. Groeneveld, "A look-up table for fully developed film-boiling heat transfer", Nuclear Engineering and Design, 225, pp.83~97 (2003)[DOI]
- "Critical Heat Flux Data Used to Generate the 2006 Groeneveld Lookup Tables, NUREG/KM-0011" (2019)[URL]
- S. Ishiyama, "Study of steam, helium and supercritical CO2 turbine power generations in prototype fusion power reactor", Progress in Nuclear Energy, 50, pp.325~332 (2008)[DOI]
- J. Qiao, "Design and optimization of intermediate heat exchanger for lead-bismuth cooled fast reactor coupled with supercritical carbon dioxide Brayton cycle", Nuclear Engineering and Design, 414, pp.112535~ (2023)[DOI]
- Y. Kato, "Medium temperature carbon dioxide gas turbine reactor", Nuclear Engineering and Design, 230, pp.195~207 (2004)[DOI]
- Y. Ahn, "Review of supercritical CO2 power cycle technology and current status of research and development", Nuclear Engineering and Technology, 47, pp.647~661 (2015)[DOI]
- "W¨armeübergang von Wasser in vertikalen Rohrstromungen ¨ bei überkritischem Druck, Forschungszentrum Karlsruhe" (2007)[URL]
- M. F. Loewenberg, "Supercritical water heat transfer in vertical tubes : a look-up table", Progress in Nuclear Energy, 50, pp.532~538 (2008)[DOI]
- X. Liu, "Look-up table establishment of supercritical water heat transfer in vertical upward flow and tube-size effect investigation", ISSCWR-5 the 5th International Symposium on Supercritical-Water-Cooled Reactors, Canadian Nuclear Society (2011)
- H. A. M. Zahlan, "Derivation of a Look-Up Table for Trans-critical Heat Transfer in Water-Cooled Tubes", PhD, pp.2015
- H. Zahlan, "A look-up table for trans-critical heat transfer in water-cooled tubes", Nuclear Engineering and Design, 285, pp.109~125 (2015)[DOI]
- F. Chang, "Look-up table for wall temperature of vertically-upward round tube with heat transfer to supercritical water", Applied Thermal Engineering, 197, pp.117440~ (2021)[DOI]
- H. Wang, "Experimental investigation of heat transfer from a 2 × 2 rod bundle to supercritical pressure water", Nuclear Engineering and Design, 275, pp.205~218 (2014)[DOI]
- H. Y. Gu, "Experimental studies on heat transfer to supercritical water in 2 × 2 rod bundle with two channels", Nuclear Engineering and Design, 291, pp.212~223 (2015)[DOI]
- H. Y. Gu, "Experimental studies on heat transfer to supercritical water in 2x2 rod bundle", 7th International Symposium on Supercritical Water-Cooled Reactors, pp.557~582 (2015)
- H. Wang, "Experiments of heat transfer to supercritical water in a 2x2 rod bundle with wire-wrapped spacers", 7th International Symposium on Supercritical Water-Cooled Reactors, pp.683~695 (2015)
- H. Wang, "Heat transfer from a 2 × 2 wire-wrapped rod bundle to supercritical pressure water", International Journal of Heat and Mass Transfer, 97, pp.486~501 (2016)[DOI]
- Z. X. Hu, "Experimental study on heat transfer of supercritical water flowing upward and downward in 2 × 2 rod bundle with wrapped wire", Annals of Nuclear Energy, 111, pp.50~58 (2018)[DOI]
- V. I. Deev, "Heat transfer in rod bundles cooled by supercritical water – experimental data and correlations", Thermal Science and Engineering Progress, 15, pp.100435~ (2020)[DOI]
- X. Cheng, "A simplified method for heat transfer prediction of supercritical fluids in circular tubes", Annals of Nuclear Energy, 36, pp.1120~1128 (2009)[DOI]
- S. Mokry, "Development of supercritical water heat-transfer correlation for vertical bare tubes", Nuclear Engineering and Design, 241, pp.1126~1136 (2011)[DOI]
- S. Gupta, "Icone19-43503 developing a heat-transfer correlation for supercriticalwater flowing in vertical tubes and its application in SCWRs", 19th International Conference on Nuclear Engineering (ICONE-19) (2011)
- X. Liu, "Wide-ranged heat transfer correlations of supercritical water in vertical upward channels", Nucl. Sci. Eng, 32, pp.344~354 (2012)
- W. Chen, "A new heat transfer correlation for supercritical water flowing in vertical tubes", International Journal of Heat and Mass Transfer, 78, pp.156~160 (2014)[DOI]
- C. Wang, "Evaluation of the heat transfer correlations for supercritical pressure water in vertical tubes", Heat Transfer Engineering, 35 (2014)[DOI]
- A.A. Bishop, "Forced-convection Heat Transfer to Water at Near-Critical Temperatures and Supercritical Pressures" (1964), Westinghouse Electric Corporation
- J. D. Jackson, "Turbulent Forced Convection in Channels and Bundles", pp.563~612 (1979), Hemisphere Publishing Corp.
- V. A. Kurganov, "Calculation of normal and deteriorated heat transfer in tubes with turbulent flow of liquids in the near-critical and vapour region of state", Thermal Engineering, 32, pp.332~336 (1985)
- V. I. Deev, "Universal dependencies for the description of heat transfer regimes in turbulent flow of supercritical fluids in channels of various geometries", The Journal of Supercritical Fluids, 135, pp.160~167 (2018)[DOI]