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Technical Paper

Hydraulics of Blocked Rod Bundles

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Pages 444-453 | Published online: 10 May 2017

References

  • A. N. DeSTORDEUR, “Drag Coefficients for Fuel-Element Spacers,” Nucleonics, 19, 6, 74 (1961).
  • K. REHME, “Pressure Drop of Spacer Grids in Smooth and Roughened Rod Bundles,” Nucl. Technol., 31, 314 (1977).
  • M. J. LOFTUS, L. E. HOCHREITER et al., “PWR FLECHT SEASET 21-Rod Bundle Flow Blockage Task Data and Analysis Report,” NUREG/CR-2444, U.S. Nuclear Regulatory Commission (1982).
  • L. F. MOODY, “Friction Factors for Pipe Flow,” Trans. ASME, 66, 8, 671 (1944).
  • J. MAREK, K. MAUBACK and K. REHME, “Heat Transfer and Pressure Drop Performance of Rod Bundles Arranged in Square Arrays,” Int. J. Heat Mass Transfer, 16, 2215 (1973).
  • A. C. SPENGOS, “Tests on Models of Nuclear Reactor Elements IV, Model of Fuel Element Supports,” UMRI-2431-4-P, University of Michigan (1959).
  • K. REHME, Institut für Neutronenphysik und Reaktortechnik, Kernforschungszentrum Karlsruhe, Private Communication (1981).
  • S. C. YAO, L. E. HOCHREITER and W. J. LEECH, “Heat Transfer Augmentation in Rod Bundles Near Grid Spacers,” J. Heat Transfer, Trans. ASME, 104, 1, 76 (1982).

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