Ex-Reactor Determination of Thermal Contact Conductance between Uranium Dioxide:Zircaloy-4 Interfaces

  • S. Begej
  • J. E. Garnier
  • A. O. Desjarlais
  • R. P. Tye


A scoping study was performed using a modified longitudinal design apparatus to investigate the effects of contact pressure (0 to 14.68 MN/m2), surface roughness, and surface error-of-form on the contact conductance between depleted uranium dioxide and Zircaloy-4. The results are compared to four existing contact conductance models which assume that the contact conductance depends on the surface roughness and elastic/plastic deformation of surface asperities. The model by Mikic-Todreas was found to best fit the data. It was also found that the pressure exponent depends on the contact pressure, surface roughness, and surface error-of-form rather than being independent of these parameters as assumed by the models. The data is also found to qualitatively fit the model by Dundurs and Panek which thereby suggests that the surface error-of-form may be the predominant factor in predicting the contact conductance, rather than the surface roughness. It is also observed that the fluid (i.e., gas) conductance rather than the contact conductance constituted the major contribution to the total interface conductance in the contact pressure range studied.


Contact Pressure Uranium Dioxide Contact Conductance Thermal Contact Conductance Interfacial Thermal Conduc 
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  1. 1.
    J. E. Garnier, S. Begej, A. O. Desjarlais, and R. P. Tye, “Ex-Reactor Determination of Thermal Gap Conductance Between Uranium Dioxide:Zircaloy-4 Interfaces,” Presented at the 16th International Conductivity Conference, Chicago, IL, November 7–9, 1979.Google Scholar
  2. 2.
    J. T. A. Roberts et al., Planning Support Document for the EPRI LWR Fuel Performance Program, EPRI-NP-737-SR, Electric Power Research Institute, Palo Alto, CA, pp. 48–52, 1978.Google Scholar
  3. 3.
    D. D. Lanning, et al, GAPCON-THERMAL-3: Code Description, PNL-2434, Pacific Northwest Laboratory, Richland, WA 99352, January 1978.Google Scholar
  4. 4.
    C. E. Beyer, C. R. Hann, D. D. Lanning, F. E. Panisko, and L. J. Parchen, GAPCON-THERMAL-II: A Computer Program for Calculating the Thermal Behavior of an Oxide Fuel Rod, BNWL-1898, Pacific Northwest Laboratory, Richland, WA 99352, 1975.Google Scholar
  5. 5.
    J. A. Dearien et al., FRAP-S2: A Computer Code for the Steady State Analysis of Oxide Fuel Rods, TREE-NUREG-1107, Nuclear Regulatory System, July 1977.Google Scholar
  6. 6.
    J. Wordsworth, “IAMBUS-1-A Digital Computer Code for the Design, In-Pile Performance Prediction and Postirradiation Analysis of Arbitrary Fuel Rods,” Nuclear Science and Engineering 31: 309, 1974.CrossRefGoogle Scholar
  7. 7.
    M. Jakob, Heat Transfer. John Wiley and Sons, Vol. 1, 1949.Google Scholar
  8. 8.
    J. E. Garnier and S. Begej, Ex-Reactor Determination of Thermal Gap and Contact Conductance Between Uranium Dioxide:Zircaloy-4 Interfaces. Stage I: Low Gas Pressure, NUREG/CR-0330, PNL-2696, Pacific Northwest Laboratory, Richland, WA 99352, April 1979.Google Scholar
  9. 9.
    A. M. Ross and R. L. Stoute, Heat Transfer Coefficient Between UO2 and Zircaloy-2, CRFD-1075, AECL-1552, Atomic Energy of Canada Limited, Chalk River, Ontario, 1962.Google Scholar
  10. 10.
    R. A. Dean, Thermal Contact Conductance Between UO2 and Zircaloy-2, CVNA-127, Westinghouse Electric Corporation, Atomic Power Division, May 1962.Google Scholar
  11. 11.
    A. C. Rapier, T. M. Jones, and J. E. McIntosh, “The Thermal Conductance of Uranium Dioxide/Stainless Steel Interfaces,” Int. J. Heat Mass Transfer 6: 397–416, 1963.CrossRefGoogle Scholar
  12. 12.
    D. D. Lanning and C. R. Hann, Review of Methods Applicable to the Calculation of Gap Conductance in Zircaloy-Clad U07 Fuel Rods, BNWL-1894, Pacific Northwest Laboratory, Richland, WA 99352, April 1975.Google Scholar
  13. 13.
    I. Peggs, J. Nucl. Matl. 57: 246–248, 1975.CrossRefGoogle Scholar
  14. 14.
    J. Dundurs and C. Panek, “Heat Conduction Between Bodies with Wavy Surfaces,” Int. J. Heat Mass Transfer 19: 731–736, 1976.CrossRefGoogle Scholar
  15. 15.
    D. R. Olander, Fundamental Aspects of Nuclear Reactor Fuel Elements, TID-26711-P1, Technical Information Center, COE, Oak Ridge, TN, April 1976.CrossRefGoogle Scholar
  16. 16.
    D. B. Scott, Physical and Mechanical Properties of Zircaloy 2 and 4, WCAP-3269–41, Westinghouse Electric Corporation, Atomic Power Division, Pittsburgh, PA, May 1965.Google Scholar

Copyright information

© Purdue Research Foundation 1983

Authors and Affiliations

  • S. Begej
    • 1
  • J. E. Garnier
    • 1
  • A. O. Desjarlais
    • 2
  • R. P. Tye
    • 2
  1. 1.Pacific Northwest LaboratoryRichlandUSA
  2. 2.Dynatech R&D Co.CambridgeUSA

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