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TECHNICAL PAPERS: Forced Convection

Measurement of the Heat Transfer Coefficient for Mercury Flowing in a Narrow Channel

[+] Author and Article Information
J. M. Crye, A. E. Ruggles, W. D. Pointer

University of Tennessee, Department of Nuclear Engineering, Knoxville, TN 37996-2300

D. K. Felde, P. A. Jallouk, M. T. McFee, M. W. Wendel, G. L. Yoder

Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831

J. Heat Transfer 124(6), 1034-1038 (Dec 03, 2002) (5 pages) doi:10.1115/1.1518500 History: Received June 14, 2001; Revised July 23, 2002; Online December 03, 2002
Copyright © 2002 by ASME
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References

Smith,  A. R., and Thompson,  E. S., 1942, “The Mercury-Vapor Process,” Trans. ASME, 64(2), pp. 625–646.
Hackett,  H. N., 1942, “Mercury for the Generation of Light, Heat, and Power,” Trans. ASME, 64(2), pp. 647–656.
Lyon,  R. N., 1951, “Liquid Metal Heat-Transfer Coefficients,” Chem. Eng. Prog., 47, pp. 75–79.
Siman-Tov, M., et al., 1998, “Thermal-Hydraulics of the Liquid Mercury Target for the Spallation Neutron Source (SNS),” Proc. 2nd Int. Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp’ 98), American Nuclear Society, La Grange Park, IL, pp. 417–427.
Jallouk, P. A., et al., 2000, “MTHL Water-Cooled Test Section Report,” Spallation Neutron Source TSR-196, Oak Ridge, TN.
Crye, J. M., et al., 2000, “MTHL Electrically-Heated (Straight) Test Section Report,” Spallation Neutron Source TSR-200, Oak Ridge, TN.
Crye, J. M., et al., 2000, “Mercury Thermal Hydraulic Loop (MTHL) Final Report” Spallation Neutron Source TSR-209, Oak Ridge, TN.
Sineath, H. H., 1949, “Heat Transfer to Mercury—The Asymmetric Case,” M.S. thesis, University of Tennessee, Knoxville, TN.
Lyon, R. N., 1949, “Forced Convection Heat Transfer Theory and Experiments with Liquid Metals,” ORNL 361, Tech. Div., Eng. Res. Section, Oak Ridge National Laboratory; Oak Ridge, TN.
Trefethen, L. M., 1950, “Heat Transfer Properties of Liquid Metals,” NP 1788, Tech. Info. Service, United States Atomic Energy Commission.
Elser, D., 1949, “Heat Transfer Measurements with Mercury,” University of California, Institute of Engineering Research, Berkeley, CA.
Stromquist, W. K., 1953, “Effect of Wetting on Heat Transfer Characteristics of Liquid Metals,” ORO-93, Tech. Info. Service, United States Atomic Energy Commission.
English, D., and Barrett, T., 1950, “Heat Transfer Properties of Mercury,” E/R-547, Atomic Energy Research Establishment, Harwell, Berkshire, UK.
Styrikovich,  M. A., and Semenovker,  I. E., 1940, “Heat Exchange at Very Low Prandtl Numbers,” J. Tech. Phys., X(16), pp. 1324–1330.
Seban, R. A., 1950, “Heat Transfer Measurements on Load Bismuth Eutectic in Turbulent Pipe Flow,” University of California, Institute of Engineering Research, Berkeley, CA.
Johnson, H. A., Hartnett, J. P., and Clabaugh, W. J., 1951, “Heat Transfer to Molten Lead-Bismuth Eutectic in Turbulent Pipe Flow,” final report, University of California, Institute of Engineering Research, Berkeley, CA.
Johnson,  H. A., Hartnett,  J. P., and Clabaugh,  W. J., 1953, “Heat Transfer to Molten Lead-Bismuth Eutectic in Turbulent Pipe Flow,” Trans. ASME, 75(6), pp. 1191–1198.
Isakoff, S. E., 1952, “Heat and Momentum Transfer in Turbulent Flow of Mercury,” Ph. D. thesis, Columbia University, New York.
MacDonald,  W. C., and Quittenton,  R. C., 1954, “A Critical Analysis of Metal ‘Wetting’ and Gas Entrainment in Heat Transfer to Molten Metals,” Heat Transfer Research Studies for 1954, Chemical Engineering Progress Symposium Series, 50(9), pp. 59–67.
Lubarsky, B., and Kaufman, S., 1956, “Review of Experimental Investigations of Liquid-Metal Heat Transfer,” Report 1270, National Advisory Committee for Aeronautics, GPO, Washington D.C.
Bauer, G. S., 1995, “European Spallation Source (ESS)—Liquid Metal Target Studies,” ESS95-33T.
Cords, H., 1998, “A Literature Survey of Fluid Flow Data for Mercury-Constitutive Equation,” ESS98-81-T.
Fleitman,  A. H., and Weeks,  J. R., 1971, “Mercury as a Mercury Coolant,” Nucl. Eng. Des., 16, pp. 266–278.
Lyon, R. N., 1952, Liquid Metals Handbook, Atomic Energy Commission, Washington, DC.
Lide, D. R., and Kehiaian, H. V., 1994, CRC Handbook of Thermophysical and Thermochemical Data, CRC Press.

Figures

Grahic Jump Location
Loop elevation (units in inches)
Grahic Jump Location
Electrically heated test section design
Grahic Jump Location
Schematic of heater block showing thermocouple locations (dimensions in mm)
Grahic Jump Location
Nusselt number versus Peclet number for various heat transfer studies in liquid metals
Grahic Jump Location
Three-dimensional computational prediction of heat flux as a function of axial length in the heated part of the channel, velocity=3.5 m/s, average flux is 840 kW/m2

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