Measurement of the Heat Transfer Coefficient for Mercury Flowing in a Narrow Channel-Reference-Cited by-同舟云学术

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

Published:2002-12-01 Issue:6 Volume:124 Page:1034-1038
ISSN:0022-1481
Container-title:Journal of Heat Transfer
language:en
Short-container-title:

Author:

Crye J. M.¹,Ruggles A. E.¹,Pointer W. D.¹,Felde D. K.²,Jallouk P. A.²,McFee M. T.²,Wendel M. W.²,Yoder, G. L.²

Affiliation:

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

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

Abstract

The heat transfer coefficient is inferred from measurements for mercury flowing in a channel of cross-section 2 mm×40 mm with flow velocities from 1 m/s to 4 m/s and heat fluxes from 192 kW/m2 to 1.14 MW/m2. Mercury bulk temperatures vary from 67°C to 143°C. Inferred heat transfer coefficients agree with open literature tube data when compared on a Nusselt versus. Peclet number plot, with Nusselt numbers examined from 8 to 17 and Peclet numbers examined from 790 to 3070.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science

Link

http://asmedigitalcollection.asme.org/heattransfer/article-pdf/124/6/1034/5789602/1034_1.pdf

Reference25 articles.

1. Smith, A. R., and Thompson, E. S., 1942, “The Mercury-Vapor Process,” Trans. ASME, 64(2), pp. 625–646.

2. Hackett, H. N. , 1942, “Mercury for the Generation of Light, Heat, and Power,” Trans. ASME, 64(2), pp. 647–656.

3. Lyon, R. N. , 1951, “Liquid Metal Heat-Transfer Coefficients,” Chem. Eng. Prog., 47, pp. 75–79.

4. 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.

5. Jallouk, P. A., et al., 2000, “MTHL Water-Cooled Test Section Report,” Spallation Neutron Source TSR-196, Oak Ridge, TN.

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