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Technical Papers

Experimental Investigation of Single- and Two-Phase Diversion Cross Flow in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR

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Pages 175-186 | Received 01 May 2017, Accepted 03 Jun 2017, Published online: 09 Aug 2017

References

  • R. T. LAHEY Jr. and F. J. MOODY, The Thermal Hydraulics of a Boiling Water Nuclear Reactor, 2nd ed. American Nuclear Society, La Grange Park, Illinois (1993).
  • A. KAWAHARA et al., “Single- and Two-Phase Diversion Cross-Flows Between Triangle Tight Lattice Rod Bundle Subchannels—Data on Flow Resistance and Interfacial Friction Coefficients for the Cross-Flow,” J. Power Energy Syst., 1, 1, 111 (2007); https://doi.org/10.1299/jpes.1.111.
  • A. TAPUCU, “Studies on Diversion Cross-Flow Between Two Parallel Channels Communicating by a Lateral Slot. I: Transverse Flow Resistance Coefficient,” Nucl. Eng. Des., 42, 297 (1977); https://doi.org/10.1016/0029-5493(77)90191-1.
  • J. S. McNOWN, “Mechanics of Manifold Flow,” ASCE Trans, 119, 1103 (1954).
  • T. G. CHAPMAN, “Pressure Equalization by Fluid Exchange Between Parallel Flow Channels,” ORNL-TM-456, Oak Ridge National Laboratory (1963).
  • R. T. DITTRICH and C. C. GRAVES, “Discharge Coefficients for Combustor-Liner Air-Entry Holes—I,” NACA-TN-3663, National Advisory Committee for Aeronautics (1956).
  • R. T. DITTRICH, “Discharge Coefficients for Combustor-Liner Air-Entry Holes—II,” NACA-TN-3924, National Advisory Committee for Aeronautics (1958).
  • M. P. SHARMA and A. K. NAYAK, “Determination of Single-Phase Turbulent Mixing Rate in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR,” Nucl. Sci. Eng., 180, 2, 172 (2015); https://doi.org/10.13182/NSE14-102.
  • D. K. CHANDRAKER, “Study on Critical Power for Advanced Heavy Water Reactor,” PhD Thesis, Tokyo Institute of Technology Department of Nuclear Engineering (2012).
  • D. K. CHANDRAKER, A. K. NAYAK, and P. K. VIJAYAN, “Development and Validation of Methodology for Dryout Modeling in BWR Fuel Assemblies and Application to AHWR Design,” BARC Newsl., 333, 19 (2013).
  • P. R. BEVINGTON and D. K. ROBINSON, Data Reduction and Error Analysis for the Physical Sciences, 3rd ed., McGraw-Hill, New York (2003).
  • S. KIM and G. C. PARK, “Numerical Determination of Lateral Loss Coefficient for Subchannel Analysis in Nuclear Fuel Bundle,” J. Korean Nucl. Soc., 27, 4, 491 (1995).
  • T. IWAMURA, H. ADACHI, and M. SOBAJIMA, “Air-Water Two-Phase Cross Flow Resistance in Rod Bundle,” J. Nucl. Sci. Technol., 23, 7, 658 (1986); https://doi.org/10.1080/18811248.1986.9735034.

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