Two-phase turbulent mixing and buoyancy drift in rod bundles

Nuclear Engineering and Design

Volumn 227, Issue 1, 2004, Pages 65-84

  Carlucci, L N ^a   Hammouda, N ^a   Rowe, D S ^b  

^a ATOMIC ENERGY OF CANADA LIMITED   (Canada)

^b Rowe and Associates   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BUOYANCY; ENTHALPY; HEAT FLUX; HYDRAULICS; PLASTIC FLOW; THERMAL EFFECTS; TURBULENCE; TWO PHASE FLOW;

CRITICAL HEAT FLUX (CHF); TURBULENT MIXING;

NUCLEAR REACTORS;

EID: 0242440208     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.08.003     Document Type: Article

References (33)

1. Barnea D. A unified model for predicting flow-pattern transitions for the whole range of pipe inclinations. Int. J. Multiphase Flow. 13:1987;1-12.
2. Barnea D., Shosham O., Taitel Y. Flow pattern transition for vertical downward two phase flow. Chem. Eng. Sci. 37:1982;741-744.
3. Carver, M.B., Kiteley, J.C., Zhou, R.Q.N., Junop, S.V., Rowe, D.S., 1995. Validation of the ASSERT subchannel code: prediction of critical heat flux in standard and nonstandard CANDU bundle geometries. Nucl. Technol. 112, pp. 299-314.
4. Chisholm D. Research note: void fraction during two-phase flow. J. Mechan. Eng. Sci. 15:1973;235-236.
5. Fighetti, C.F., Reddy, D.G., 1982. Experimental determination of subchannel mass flow rate and enthalpy in rod bundles. In: Tube Bundle Thermal-Hydraulics. ASME, pp. 63-73.
6. Gustafson, B., Harju, R., Imset, O., 1974. Flow and enthalpy distribution in a 9-rod bundle. In: European Two-Phase Flow Meeting, Harwell, SDS-82, AE-RL-1544, May 22.
7. Herkenrath, H., Hufschmidt, W., Jung, U., Weckermann, F., 1981. Experimental Investigation of the Enthalpy and Mass Flow - Distribution in 16-Rod Clusters with BWR-PWR - Geometries and Conditions. Commission of the European Communities, Ispra Joint Research Centre Report, EUR 7575 EN.
8. Ingesson, L., Hedberg, S., 1970. Heat transfer between subchannels in a rod bundle. In: Heat Transfer, vol. 3. Elsevier, Amsterdam.
9. Kawahara A., Sato Y., Sadatomi M. The turbulent mixing rate and the fluctuations of static pressure difference between adjacent subchannels in a two-phase subchannel flow. Nucl. Eng. Des. 175:1997;97-106.
10. Lahey Jr., R.T., Moody, F.J., 1993. The Thermalhydraulics of a Boiling Water Nuclear Reactor, 2nd ed. American Nuclear Society (Chapter 4).
11. Lahey Jr., R.T., Shirilkar, B.S., Radcliffe, D.W., 1970. Two-Phase Flow and Heat Transfer in Multi-Rod Geometries: Subchannel and Pressure Drop Measurements in a Nine-Rod Bundle for Diabatic and Adiabatic Conditions. General Electric AEC Research and Development Report, GEAP-13049.
12. Marek, J., Rehme, K., 1979. Heat transfer in smooth and roughened rod bundles near spacer grids. In: Yao, S., Pfund, P. (Eds.), Fluid Flow and Heat Transfer Over Rod or Rube Bundles. ASME.
13. Rehme, K., 1973. Pressure drop correlations for fuel element spacers. Nucl. Technol. 17, pp. 15-23.
14. Rehme, K., 1992. The structure of turbulence in rod bundles and the implications on natural mixing between subchannels. Int. J. Heat Mass Transfer 35, pp. 567-581.
15. Rogers, J.T., Rosehart, R.G., 1972. Mixing by Turbulent Interchange in Fuel Bundles, Correlations and Inferences. ASME 72-HT-53.
16. Rogers, J.T., Tahir, A.E.E., 1975. Turbulent Interchange Mixing in Rod Bundles and the Role of Secondary Flows. ASME 75-HT-31.
17. Rogers, J.T., Todreas, N.E., 1968. Coolant interchannel mixing in reactor fuel rod bundles - single phase coolants. In: Heat Transfer in Rod Bundles. ASME.
18. Rowe, D.S., Angle, C.W., 1967 Cross Flow Mixing Between Parallel Flow Channels During Boiling. Part II: Measurement of Flow Enthalpy in Two Parallel Channels. Pacific Northwest Laboratory, Richland, WA, BNWL-371 Part 2.
19. Rowe, D.S., Angle, C.W., 1969 Crossflow Mixing Between Parallel Flow Channels During Boiling. Part III: Effect of Spacers on Mixing Between Two Channels, Battelle Northwest, BNWL-371 Part 3.
20. Rowe, D.S., Macduff, R.B., Collingham, R.E., 1990. Thermalhydraulic Subchannel Model Based on Void Drift. Paper No. 9-TPF-02. Ninth International Heat Transfer Conference, Jerusalem, Israel.
21. Rudzinski, K.F., 1970. Two-Phase Turbulent Mixing for Air-Water Flows in Adjacent Triangular Subchannels. M.Sc. Department of Chemical Engineering, University of Windsor.
22. Sadatomi, M., Kawahara, A., Sato, Y., 1995. Turbulent mixing of both gas and liquid phases between subchannels in two-phase hydrodynamically equilibrium flows. In: Celata, G.P., Shah, R.K. (Eds.), Proceedings of the International Symposium Two-Phase Flow Modelling and Experimentation, vol. 1, Rome, pp. 403-409.
23. Singh, K.S., 1972. Air-Water Turbulent Mixing in Simulated Rod Bundle Geometries. Ph.D. Thesis, Department of Chemical Engineering, University of Windsor.
24. Sterner, R.W., Lahey Jr., R.T., 1983. Air-Water Subchannel Measurements of the Equilibrium Quality and Mass Flux Distribution in a Rod Bundle. U.S. Nuclear Regulatory Commission Report, REP/NUREG-CR-3373/1983.
25. Tapucu A., Teyssedou A., Tye P., Troche N. The effect of turbulent mixing models on the prediction of subchannel codes. Nucl. Eng. Des. 149:1994;221-231.
26. Tye P., Teyssedou A., Tapucu A. An investigation of the constitutive relations for intersubchannel transfer mechanisms in horizontal flows as applied in the ASSERT-4 subchannel code. Nucl. Eng. Des. 149:1994;207-220.
27. Wallis, G.B., 1969. One-Dimensional Two-Phase Flow. McGraw Hill.
28. Walton, F.B., 1969. Turbulent Mixing Measurements for Single-Phase Air, Single-Phase Water, and Two-Phase Air-Water Flows in Adjacent Triangular Subchannels. M.Sc. Thesis, Department of Chemical Engineering, University of Windsor.
29. Weisman, J., Bowring, R.W., 1975. Methods for detailed thermalhydraulic analysis of water-cooled reactors. Nucl. Sci. Eng. 57, pp. 255-276.
30. Wolf L., Fischer K., Herkenrath H., Hufschmidt W. Comprehensive assessment of the ISPRA BWR and PWR subchannel experiments and code analysis with different two-phase models and solution schemes. Nucl. Eng. Des. 99:1987;329-350.
31. Yang, S.K., Chung, M.K., 1995. Turbulent flow through mixed spacer grids in rod bundles. In: 1995 National Heat Transfer Conference, HTD, vol. 316. ASME.
32. Yao, S.C., Hochreiter, L.E., Leech, W.J., 1982. Heat-transfer augmentation in rod bundles near spacer grids. Journal of Heat Transfer 104, pp. 76-102.
33. Yin, S.T., Tain, R.M., Chukkapalli, G., Sutradhar, S.C., 1999. An experimental investigation of enthalpy/void migration in an equally heated twin-subchannel assembly. In: Ninth International Meeting on Nuclear Reactor Thermalhydraulics, San Francisco, October 3-8.