Development of supercritical water heat-transfer correlation for vertical bare tubes

Nuclear Engineering and Design

Volumn 241, Issue 4, 2011, Pages 1126-1136

  Mokry, Sarah ^a   Pioro, Igor ^a   Farah, Amjad ^a   King, Krysten ^a   Gupta, Sahil ^a   Peiman, Wargha ^a   Kirillov, Pavel ^b  

^a UNIVERSITY OF ONTARIO INSTITUTE OF TECHNOLOGY   (Canada)

^b INSTITUTE OF PHYSICS AND POWER ENGINEERING   (Russian Federation)

Author keywords

AECL; Atomic Energy of Canada Limited; Canada deuterium uranium (reactor); CANDU; deteriorated heat transfer; DHT; Generation IV International Forum; GIF; heat transfer coefficient; HTC; ID; inside diameter; National Institute of Standards and Technology; NIST; NPP; nuclear power plant; pressure tube (reactor); pressure vessel (reactor); PT; PV; RMS; root mean square; SCW; SCWR; shear stress transport (k model); SST; supercritical water reactor; supercritical water cooled; VVER SCP; water water power reactor of supercritical pressure (in Russian abbreviations)

Indexed keywords

AECL; ATOMIC ENERGY OF CANADA LIMITED; CANADA DEUTERIUM URANIUM (REACTOR); CANDU; DETERIORATED HEAT-TRANSFER; DHT; GENERATION IV INTERNATIONAL FORUM; GIF; HTC; ID; INSIDE DIAMETER; NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY; NIST; NPP; NUCLEAR POWER; PT; PV; RMS; ROOT MEAN SQUARE; SCW; SCWR; SST; SUPERCRITICAL WATER; SUPERCRITICAL WATER REACTORS; VVER-SCP; WATER-WATER POWER REACTOR OF SUPERCRITICAL PRESSURE (IN RUSSIAN ABBREVIATIONS);

COMPUTATIONAL FLUID DYNAMICS; CORRELATION METHODS; DEUTERIUM; HEAT TRANSFER COEFFICIENTS; LIGHT WATER REACTORS; MOLECULAR PHYSICS; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; NUCLEAR PROPULSION; NUSSELT NUMBER; PRESSURE TUBE REACTORS; PRESSURE VESSELS; REYNOLDS NUMBER; SHEAR STRESS; STRENGTH OF MATERIALS; TUBES (COMPONENTS); URANIUM; WATER COOLING SYSTEMS; WATER POWER;

HEAT EXCHANGERS;

EID: 79953234384     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2010.06.012     Document Type: Article

References (27)

1. A.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 super-critical pressures 1964 Westinghouse Electric Corporation Pittsburgh, PA
2. Bishop, A.A.; Sandberg, R.O.; and Tong, L.S.; 1965, Forced convection heat transfer to water at near-critical temperatures and supercritical pressures, A.I.Ch.E.-I.Chem.E Symposium Series No. 2, pp. 77-85.
3. F.W. Dittus, and L.M.K. Boelter Heat transfer in automobile radiators of the tubular type University of California, Berkeley, Publications on Engineering 2 13 1930 443-461
4. R. Duffey, I. Pioro, and T. Zhou Supercritical water-cooled nuclear reactors (SCWRs): current and future concepts - steam-cycle options Proc. ICONE-16 Orlando, FL, USA, May 11-15, Paper #48869 2008 9
5. B.V. Dyadyakin, and A.S. Popov Heat transfer and thermal resistance of tight seven-rod bundle, cooled with water flow at supercritical pressures Transactions of VTI 11 1977 244 253 (in Russian)
6. Y. Gospodinov, S. Mokry, I. Pioro, and P.L. Kirillov Supercritical water heat transfer in a vertical bare tube Proc. ICONE-16 Orlando, FL, USA, May 11-15, Paper #48546 2008 11
7. J.D. Jackson Consideration of the heat transfer properties of supercritical pressure water in connection with the cooling of advanced nuclear reactors Proc. 13th Pacific Basin Nuclear Conference Shenzhen City, China, October 21-25 2002
8. P. Kirillov, R. Pometko, and A. Smirnov Experimental study on heat transfer to supercritical water flowing in 1- and 4-m-long vertical tubes Proc. GLOBAL '05 Tsukuba, Japan, October 9-13, Paper No. 518 2005
9. E. Krasnoshchekov, V. Protopopov, F. Van, and I. Kuraeva Experimental investigation of heat transfer for carbon dioxide in the supercritical region C. Gazley Jr. J. Harnett, E. Ecker, Proc. 2nd All-Soviet Union Conf. on Heat and Mass Transfer Minsk, Belarus, May 1964, vol. 1 1967 26 35 Published as Rand Report R-451-PR
10. R.A. Lee, and K.H. Haller Supercritical water heat transfer developments and applications Proceedings of the 5th International Heat Transfer Conference Tokyo, Japan, September 3-7, vol. IV Paper No. B7.7 1974 335 339
11. W. McAdams Heat Transmission second ed. 1942 McGraw-Hill New York, NY, USA 459 pp
12. S. Mokry, Y. Gospodinov, I. Pioro, and P.L. Kirillov Supercritical water heat-transfer correlation for vertical bare tubes Proc. ICONE-17 Brussels, Belgium, July 12-16, Paper #76010 2009 8
13. S. Mokry, A. Farah, K. King, S. Gupta, I. Pioro, and P. Kirillov Development of supercritical water heat-transfer correlation for vertical bare tubes Proceedings of the Nuclear Energy for New Europe International Conference Bled, Slovenia, September 14-17, Paper No. 210 2009
14. B. Munson, D. Young, and Th. Okiishi Fundamentals of Fluid Mechanics fifth ed. 2005 J. Wiley & Sons New York, NY
15. M. Naidin, S. Mokry, and F. Baig Thermal-design options for pressure-channel SCWRs with co-generation of hydrogen Journal of Engineering for Gas Turbines and Power 131 January 2009 8
16. M. Naidin, I. Pioro, and U. Zirn Supercritical water-cooled NPPs with co-generation of hydrogen: general layout and thermodynamic-cycles options Proc. 4th Int. Symp. on Supercritical Water-Cooled Reactors Heidelberg, Germany, March 8-11, Paper No. 78 2009 11
17. National Institute of Standards Technology NIST Reference Fluid Thermodynamic and Transport Properties-REFPROP: NIST Standard Reference Database 23, Ver. 8.0 2007 Department of Commerce Boulder, CO, USA
18. I. Pioro, and R. Duffey Heat Transfer and Hydraulic Resistance at Supercritical Pressures in Power Engineering Applications 2007 ASME Press New York, NY, USA 334 pp
19. I.L. Pioro, P.L. Kirillov, S.J. Mokry, and Y.K. Gospodinov Supercritical water heat transfer in a vertical bare tube: normal, improved and deteriorated regimes Proc. ICAPP '08 Anaheim, CA, USA, June 8-12, Paper #8333 2008 1843 1852
20. E.N. Pis'mennyy, V.G. Razumovskiy, and E.M. Maevskiy Experimental study on temperature regimes to supercritical water flowing in vertical tubes at low mass fluxes Proceedings of the International Conference GLOBAL-2005 Nuclear Energy Systems for Future Generation and Global Sustainability Tsukuba, Japan, October 9-13, Paper No. 519 2005 9
21. A.F. Polyakov Mechanism and limits on the formation of conditions for impaired heat transfer at a supercritical coolant pressure High Temperatures 13 6 1975 1119 1126 (1210-1219)
22. N.M. Schnurr, V.S. Sastry, and A.B. Shapiro A numerical analysis of heat transfer to fluids near the thermodynamic critical point including the thermal entrance region Journal of Heat Transfer: Transactions of the ASME 98 4 1976 609 615
23. H.S. Swenson, J.R. Carver, and C.R. Kakarala Heat transfer to supercritical water in smooth-bore tubes Journal of Heat Transfer: Transactions of the ASME Series C 87 4 1965 477 484
24. G. Vanyukova, Y. Kuznetsov, and A. Loninov Application of CFD-code to calculations of heat transfer in a fuel bundle of SCW pressure-channel reactor Proc. 4th Int. Symp. on Supercritical Water-Cooled Reactors Heidelberg, Germany, March 8-11, Paper No. 28 2009 9
25. R.H.S. Winterton Where did the Dittus and Boelter equation come from? International Journal of Heat and Mass Transfer 41 4-5 1998 809 810 (Pubitemid 128397146)
26. K. Yamagata, K. Nishikawa, and S. Hasegawa Forced convective heat transfer to supercritical water flowing in tubes International Journal of Heat and Mass Transfer 15 12 1972 2575 2593
27. H. Zahlan, D.C. Groeneveld, and S. Tavoularis Look-up table for trans-critical heat transfer Proceedings of the 2nd Canada-China Joint Workshop on Supercritical Water-Cooled Reactors (CCSC-2010) Toronto, Ontario, Canada, April 25-28, Paper No. P036 2010