پیوندهای مفید
آمار
| تعداد نشریات | 21 |
| تعداد شماره‌ها | 640 |
| تعداد مقالات | 9,352 |
| تعداد مشاهده مقاله | 67,997,442 |
| تعداد دریافت فایل اصل مقاله | 27,158,845 |
Heat Transfer Studies of Supercritical Water Flows in an Upward Vertical Tube | ||
| Journal of Heat and Mass Transfer Research | ||
| مقاله 66، دوره 6، شماره 2 - شماره پیاپی 12، بهمن 2019، صفحه 155-167 اصل مقاله (2.09 M) | ||
| نوع مقاله: Full Length Research Article | ||
| شناسه دیجیتال (DOI): 10.22075/jhmtr.2019.17488.1229 | ||
| نویسندگان | ||
| Deenadayalan Santhosh Kumar* 1؛ Suresh S2؛ Anand Sundaravel3 | ||
| 1R&D, High Pressure Boiler Plant, Bharat Heavy Electricals Limited, Trichy, India. | ||
| 2National Institute of Technology, Trichy, India | ||
| 3Mechanical engineering, NIT Trichy,Tamilnadu, India. | ||
| تاریخ دریافت: 27 فروردین 1398، تاریخ بازنگری: 16 شهریور 1398، تاریخ پذیرش: 02 مهر 1398 | ||
| چکیده | ||
| In this paper, an investigation of heat transfer characteristics at supercritical pressure fluid flowing in a uniformly heated vertical tube has been carried out. In order to reduce thermal emissions and increase thermal efficiency, supercritical boilers were developed at various sizes. Above supercritical pressure, the distinction of liquid and gas phases disappears. This dispenses with the problem of critical heat flux and dry out phenomenon which occurs in subcritical pressure. However, the study of heat transfer behavior above supercritical pressure is indeed required due to the heat transfer deterioration operation at high heat flux to mass flux ratio. In the present work, numerical simulation has been employed in order to inquire about the effect of various parameters such as heat flux to mass flux ratio, diameter and pressure that causes heat transfer deterioration. Shear Stress Transport k-ω model has been applied in all the computations. It is observed that the metal temperature predicted by numerical simulation is more accurate than the empirical correlations available in the literature. A Visual Basic Program has also been developed to assess the empirical correlations in the context of predicting metal temperature under 5280 different operating conditions. Tube sizes of 10, 15 & 20 mm inner diameter with 4 m length, the pressure between 225 and 280 bar and heat flux to mass flux ratio between 0.27 and 0.67 have been chosen to explore the effect of diameter, pressure and heat flux respectively. | ||
| کلیدواژه‌ها | ||
| Supercritical water؛ heat transfer deterioration؛ SST-kw model؛ heat transfer enhancement؛ vertical flow | ||
| مراجع | ||
|
[1]US DOE Nuclear Energy Research Advisory Committee and Generation IV International Forum, A Technology Roadmap for Generation IV Nuclear Energy Systems, (2002).
[2]M.W. Shitsman, Heat transfer to SC helium, carbon dioxide, and water: Analysis of thermodynamic and transport properties and experimental data, Cryogenics, 14 (2), 77–83 (1974).
[3]H. Griem, A new procedure for the prediction of forced convection heat transfer at nearand SC pressure, Heat and Mass Transfer, 31 (5), 301–305 (1996).
[4]S.K. Yang and H.F. Khartabil, Normal and deteriorated heat transfer correlations for SC fluids, Transaction of the American Nuclear Society, November 13–17, Washington, D.C., USA, 93, 635–637 (2005).
[5]X. Lei, H. Li, W. Zhang, T. Dinh, Y. Guo, S. Yu, Experimental study on the difference of heat transfer characteristics between vertical and horizontal flows of supercritical pressure water, Applied Thermal Engineering, 113, 609–620 (2017).
[6]J J. Wang, H. Li, S. Yu, T. Chen, Comparison of the transfer characteristic of SC pressure water to that of subcritical pressure water in vertically-upward tubes, Int. J. Multiphase Flow, 37, 769–776 (2011).
[7]M. K. Rowinski, J. Zhao, T. J. White, Y. Ch. Soh, Numerical investigation of supercritical water flow in a vertical pipe under axially non-uniform heat flux, Progress in Nuclear Energy 97, 11-25 (2017).
[8]X. Cheng, T. Schulenberg, D. Bittermann, P. Rau, Design analysis of core assembly for supercritical pressure conditions. Nucl. Eng. Des. , 223, 279–294 (2003).
[9]R. B. Duffey, I. Pioro, X. Zhou, U. Zirn, S. Kuran, H. Khartabil, M. Naidin Supercritical WaterCooled Nuclear Reactors (SCWRs): current and future concepts – steam cycle options Icone 16, Proceeding of the 16th International Conference on Nuclear Engineering, 4, 469–477 (2008).
[10] S. Koshizuka, N.Takano, Y. Oka, Numerical analysis of deterioration phenomenon in heat transfer tosupercritical water. Int. J. Heat Mass Transfer, 38, 3077–3084 (1995).
[11] S. Mokry, I. Pioro, A. Farah, K. King,S. Gupta, W. Peimana, P. Kirillov, evelopment of supercritical water heat-transfer correlation for vertical bare tubes Nuclear Engineering and Design, 241, 1126–1136, (2011).
[12] Q. L. Wen, H. Y. Gu, Numerical simulation of heat transfer deterioration phenomenon in supercritical water through vertical tube. Annals of Nuclear Energy, 37, 1272–1280 (2010).
[13] Z. Shen, D. Yang, S.Wang, W.Wang,Y. Li, Experimental and numerical analysis of heat transfer towater at supercritical pressures, International Journal of Heat and Mass Transfer, 108, 1676–1688 (2017).
[14] S. Anand, S. Suresh, D. Santhoshkumar, Numerical study for the effect of heat and mass flux on heat transfer characteristics of supercritical water flows in a upward vertical tube Proceeding of the 24thNational and 2nd International ISHMT-ASTFE Heat and mass transfer conference (IHMTC2017)BITS Pilani, Hyderabad, India December, 27-30 (2017).
[15] S. Anand, S. Suresh, D. Santhoshkumar, Numerical study for the effect of diameter and pressure on heat transfer characteristics of supercritical water flows in a upward vertical tube International conference on Numerical Heat transfer and SL.NO Inside Diameter (mm) CASE I (q/G=0.27) CASE II (q/G=0.4) CASE III (q/G=0.67) Heat flux (q) kW/m2 Mass flux (G) (kg/ m2 s) Heat flux (q) kW/m2 Mass flux (G) (kg/ m2 s) Heat flux (q) kW/m2 Mass flux (G) (kg/ m2 s) 1 10 141 504 400 1000 334 499 2 15 141 504 400 1000 334 499 3 20 141 504 400 1000 334 499 S. Anand / JHMTR 6 (2019) 155-167 167 fluid flow NIT Warangal, India- Jan19-21 (2018).
[16] K. Yamagata, K. Nishikawa, S. Hasegawa, Forced convective heat transfer to SC water flowing in tubes, Int. J.Heat Mass Transfer, 15 , 2575– 2593 (1972).
[17] J. W. Ackerman, Pseudo-boiling heat transferto supercritical pressure water in smooth and ribbed tubes, Trans. ASME, 490–498 (1970).
[18] R. A. Lee, K. H. Haller, SCwater heat transfer developments, and applications Proc. 5th International Heat Transfer Conference, Japan, 4(7), 335–339 (1974).
[19] J. H. Song, H.Y. Kim, H. Kim, Y.Y. Bae, Heat transfer characteristics of a SC fluid flow in a vertical pipe, J. Supercrit.Fluids, 44,164–171 (2008).
[20] M. J. Watts, C. T. Chou, Mixed convection heat transfer to SC pressure water, Proceedings of the 7th International Heat Transfer Conference, Munich, Germany, 495–500 (1982).
[21] T. Yamashita, S. Yoshida, H. Mori, S.Morooka, H. Komita, K. Nishida, Heat transfer study under SC pressure conditions, ENES4/ANP2003, Kyoto, JAPAN, 11-19 (2003).
[22] D. Jackson, W. D. Haller, Influences ofbuoyancy on heat transfer to fluids flowing in vertical tubes under turbulent conditions, Turbulent Forced Convection in Channels and Rod Bundles, 2, 613–640 (1979).
[23] Y. Y. Bae, H. Y. Kim, D.J. Kang, Forced and mixed convection heat transfer to SC CO2 vertically flowing in a uniformly-heated circular tube, Exp. Thermal Fluid Sci., 34 , 1295–1308 (2010).
[24] S. Yildiz, Groeneveld Diameter effect on SC heat transfer International Communications in Heat and Mass Transfer, 54, 27–32 (2014).
[25] B. Zhu, Ch. Yang, An investigation on heat transfer characteristics of different pressure steam-water in vertical upward tube, Nuclear Engineering and Design, 239, 381– 388 (2009).
[26] B. Gang, W. Yang, H. Zhu, Experimental investigation of heat transfer for SC pressure water flowing in vertical annular channels, Nuclear Engineering and Design, 241, 4045– 4054 (2011).
[27] Shen, Xie, Nie, Liu, Wang. Flow and Heat transfer characteristics of high-pressure water flowing in a vertical upward smooth tube at low mass flux conditions, Applied Thermal Engineering, 102, 391–401 (2016).
[28] F. W. Dittus and L. M. K. Boelter, Heat Transfer in Automobile Radiators of the Tubular Type, 3rd ed. Publications in Engineering, Berkeley: University of California, 443 (1930).
[29] A. Bishop, R. O. Sandberg, and L. S. Tong, High Temperature Supercritical Pressure Water Loop. Part IV. Forced Convection Heat Transfer to Water at Near-Critical Temperatures and Supercritical Pressures, Pittsburgh, USA: Westinghouse Electric Corp. (1964).
[30] P. Ornatskij, L. F. Glushchenko and S. I.Kalachev, “Heat transfer with rising and falling flows of water in tubes of small diameter at supercritical pressures,” Therm. Eng., 18(5), 137–141 (1971).
[31] J. D. Jackson, “Consideration of the heat transfer properties of supercritical pressure water in connection with the cooling of advanced nuclear reactors,” in: Proceedings of the 13th pacific Basin Nuclear Conference, Shenzhen City, China, October 21–25 (2002).
[32] X. Lei, Y. Guo, W. Zhang, H. Li and L. Li Development of Heat Transfer Correlation for Supercritical Water in Vertical Upward Tubes heat transfer engineering, (2018).
[33] M. F. Loewenberg, E. Laurien, A. Class, T. S. Berg, Supercritical water heat transfer in vertical tubes: A look-up table Progress in Nuclear Energy, 50, 532-538 (2008).
[34] M. Jaromin, H. Anglart, A numerical study of heat transfer to supercritical water flowing upward in vertical tubes under normal and deteriorated conditions. Nuclear Engineering and Design, 264, 61– 70 (2013).
[35] T. Zhi, Ch. Zeyuan, Z. Jianqin, L. Haiwang, Effect of turbulence models on predicting convective heat transfer to hydrocarbon fuel at supercritical pressure.Chinese Journal of Aeronautics, 29 (5), 1247–1261 (2016).
[36] M. Pioro, K. Gospodinov, SC water heat transfer in a vertical bare tube, Nuclear Engineering and Design, 240, 568–576 (2010). [37] M. Sharabi, W. Ambrosini, Discussion of heat transfer phenomena in fluids at supercritical pressure with the aid of CFD models, Annals of Nuclear Energy, 60-71 (2009). | ||
|
آمار تعداد مشاهده مقاله: 687 تعداد دریافت فایل اصل مقاله: 422 |
||