11
Views
2
CrossRef citations to date
0
Altmetric
Technical Paper

Dispersed-Flow Film Boiling Heat Transfer Data near Spacer Grids in a Rod Bundle

, , &
Pages 304-313 | Published online: 13 May 2017

REFERENCES_

  • J. MAREK and K. REME, “Heat Transfer in Smooth and Roughened Rod Bundles near Spacer Grids,” Fluid Flow and Heat Transfer over Rod or Tube Bundles, S. YAO, and P. PFUND, Eds., American Society of Mechanical Engineers (1979).
  • H. W. HOFFMAN et al., “Experimental Studies of the Heat Transfer and Fluid Dynamic Characteristics of RodCluster-Type Nuclear Reactor Fuel Elements,” ORNL-4356, Oak Ridge National Laboratory (May 1970).
  • V. KRETT and J. MAJER, “Temperature Field Measurement in the Region of Spacing Elements,” ZJE-114, Skoda Works, Pilsen, Czechoslovakia (1971).
  • E. M. CLUSS, Jr., “Post Critical Heat Flux Heat Transfer in a Vertical Tube Including Spacer Grid Effects,” MS Thesis, Massachusetts Institute of Technology (June 1978).
  • P. IHLE, “Flooding Experiments in Blocked Arrays FEBA Recent Results and Future Plans,” Proc. Mtg. Water Reactor Safety Research Information, Gaithersburg, Maryland, October 27–31, 1980, U.S. Nuclear Regulatory Commission (1980).
  • D. G. MORRIS et al., “A Preliminary Evaluation of Rod Bundle Post-CHF Heat Transfer to High Pressure Water in Transient Upflow,” ORNL/CF-81/265, Oak Ridge National Laboratory (Nov. 9, 1981).
  • S. C. YAO, L. E. HOCHREITER, and W. J. LEECH, “Heat Transfer Augmentation in Rod Bundles near Grid Spacers,” Proc. ASME Winter Annual Mtg., Chicago, Illinois, November 16–21, 1980, American Society of Mechanical Engineers (1980).
  • D. C. GROENEVELD and W. W. YOUSEF, “Spacing Devices for Nuclear Fuel Bundles, A Survey of Their Effect on CHF, Post-CHF Heat Transfer and Pressure Drop,” Proc. ANS/ASME/NRC Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics, Saratoga Springs, New York, October 5–8, 1980, U.S. Nuclear Regulatory Commission (1980).
  • A. W. BENNETT et al., “Heat Transfer to Steam-Water Mixtures in Uniformly Heated Tubes in Which the Critical Heat Flux Has Been Exceeded,” AERE-R-5373, United Kingdom Atomic Energy Authority (Oct. 1967).
  • R. P. FORSLUND, “Thermal Non-Equilibrium in Dispersed Flow Film Boiling in a Vertical Tube,” PhD Thesis, Massachusetts Institute of Technology (Dec. 1966).
  • S. M. NIJHAWAN, “Experimental Investigation of Thermal Non-Equilibrium in Post-Dryout Steam-Water Flow,” PhD Thesis, Lehigh University (1980).
  • G. L. YODER et al., “Dispersed Flow Film Boiling in Rod Bundle Geometry–Steady State Heat Transfer Data and Correlation Comparisons,” ORNL-5822, Oak Ridge National Laboratory (Mar. 1982).
  • L. M. K. BOELTER, G. YOUNG, and H. W. IVERSEN, “An Investigation of Aircraft Heaters XXVII–Distribution of Heat Transfer Rate in the Entrance Section of a Circular Tube,” NACA Technical Note No. 1451, National Advisory Committee for Aeronautics (Oct. 1930).
  • R. G. DEISSLER, “Analysis of Turbulent Heat Transfer and Flow in the Entrance Region of Smooth Passages,” NACA Technical Note No. 3016, National Advisory Committee for Aeronautics (Oct. 1953).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.