Heat-transfer augmentation in rod bundles near grid spacers

Journal of Heat Transfer

Volumn 104, Issue 1, 1982, Pages 76-81

  Yao, S C ^a   Hochreiter, L E ^b   Leech, W J ^b  

^a CARNEGIE MELLON UNIVERSITY   (United States)

^b WESTINGHOUSE ELECTRIC COMPANY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

FLOW OF FLUIDS - CHANNEL FLOW;

HEAT TRANSFER;

EID: 0020089527     PISSN: 00221481     EISSN: 15288943     Source Type: Journal    
DOI: 10.1115/1.3245071     Document Type: Article

References (19)

1. Rehme, K., “Pressure Drop Correlations for Fuel Element Spacers,” Nuclear Technology, Vol. 17, 1973, pp. 15-23.
2. Rehme, K., “Pressure Drop of Spacer Grids in Smooth and Roughened Rod Bundles,” Nuclear Technology, Vol. 31, 1977, pp. 314-317.
3. Idel’chik, I.E., Handbook of Hydraulic Resistance, AEC-tr-6630, 1966.
4. De Stordeur, A. N., “Drag Coefficients for Fuel-Element Spacers,” Nucleonics, Vol. 19, No. 6, 1961, pp. 74-79.
5. De Paz, J. F., “Pressure Drop and Volume Fraction of Grid and Wire Spaced Subassemblies,” ANL-AFP-13, 1975.
6. Marek, J. and Rehme, K., “Heat Transfer in Smooth and Roughened Rod Bundles near Spacer Grids,” Fluid Flow and Heat Transfer over Rod or Tube Bundles, Edited by S. Yaoand P. Pfund, ASME, 1979, p. 163-170.
7. Conway, C. E. “PWR FLECHT Separate Effects and Systems Effects Test (SEASET) Program Plan,” NRC/EPRI/Westinghouse Report No. 1,1977.
8. Cluss, E. M., “Post Critical Heat Flux Heat Transfer in a Vertical Tube Including Spacer Grid Effects,” MIT. S. B. thesis, June, 1978.
9. Vlcek, J. and Weber, P., “The Experimental Investigation of a Local (spot) Heat Transfer Coefficient in the Fuel Spacer Area,” Australian Atomic Energy Commission Research Establishment, LIB/TRANS 250, Feb. 1970.
10. Kidd, G. J. and Hoffman, H. W., “The Temperature Structure and Heat Transfer Characteristics of an Electrically Heated Model of a Seven-Rod Cluster Fuel Element,” ASME paper 68-WA/HT-33.
11. Krett, V. and Majer, J., “Temperature Fluid Measurement in the Region of Spacing Elements,” Report ZJE-114, Skoda Works Nuclear Power Construction Dept., Information Centre Plzen-Czechoslovakia, 1971.
12. Hudina, M. and Nothigen, H., “Experiment Study of Local Heat Transfer under and near Grid Spacers Developed for GCFR,” Report TM-1N-526, Swiss Federal Institute for Reactor Research Wirenlingen, 1973 or 2nd NEA-GCFR Specialist Meeting on Heat Transfer, 1972.
13. Thorsen, R. and Landis, F., “Friction and Heat Transfer Characters in Turbulent Swirl Flow Subjected to Large Transverse Temperature Gradients,” ASME, Journal of Heat Transfer, 1968, pp. 87-97.
14. Kreith, F. and Sonju, O., “The Decay of a Turbulent Swirl in a Pipe,” Journal of Fluid Mechanics, Vol. 22, Part 2, 1965, pp. 257-271.
15. Migay, V. and Golubev, L., “Friction and Heat Transfer in Turbulent Swirl Flow with Variable Swirl Generator in a Pipe,” Heat Transfer-Soviet Research, Vol. 2, No. 3, 1970, pp. 68-73.
16. Yao, S. C. and Rane, A., “Numerical Study of Turbulent Droplet Flow Heat Transfer,” International Journal of Heat and Mass Transfer, Vol. 24, No. 5, pp. 785-792, 1981.
17. Kendall, G. E., “Heat Transfer to Impacting Drops and Post Critical Heat Flux Dispersed Flow,” Ph. D. thesis, MIT, 1978.
18. Iloeje, O. C, Plummer, D. N., Rohsenow, W. M., and Griffith, P., “A Study of Wall Reset and Heat Transfer in Dispersed Vertical Flow,” MIT Report No. 72718-92, 1974.
19. Tong, L. S. and J. Weisman, Thermal Analysis of Pressurized Water Reactors, 2nd ed., American Nuclear Society, 1979, p. 285.