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Technical Paper

Critical Heat Flux in Square- and Nonsquare-Array Rod Bundles for Advanced Light Water Reactors

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Pages 219-228 | Published online: 10 Aug 2017

References

  • “Status of Advanced Light Water Reactor Designs,” IAEA-TECDOC-1391, International Atomic Energy Agency (2004).
  • D. C. GROENEVELD et al., “The 1995 Look-Up Table for Critical Heat Flux in Tubes,” Nucl. Eng. Des., 163, 1 (1996).
  • R. ZIMMERMAN, H. KEMNER, P. SUCHY, and G. ULRYCH, “The Heated Length Effect in CHF Correlations—A Physical Reality or a Code Deficiency?” presented at Symp. Thermophysics 90, Obninsk, Russia, September 25–28, 1990.
  • D. G. REDDY and C. F. FIGHETTI, “Parametric Study of CHF Data Vol. 2. A Generalized Subchannel CHF Correlation for PWR and BWR Fuel Assemblies,” EPRI NP-2609 Vol. 2, Electric Power Research Institute (1983).
  • D. B. OWEN, “Factors for One-Sided Tolerance Limits and for Variables Sampling Plans,” SCR-607, Sandia National Laboratories (1963).
  • C. F. FIGHETTI and D. G. REDDY, “Parametric Study of CHF Data Vol. 3. Critical Heat Flux Data,” EPRI NP-2609 Vol. 3, Electric Power Research Institute (1982).
  • B. W. LETOURNEAU, A. C. PETERSON, K. J. COELING, M. E. GAVIN, and S. J. GREEN, “Critical Heat Flux and Pressure Drop Tests with Parallel Upflow of High Pressure Water in Bundles of Twenty 0.25 and 0.28 Inch Diameter Rods,” WAPD-TM-1013, Bettis Atomic Power Laboratory (1975).
  • L. S. TONG, “Boiling Crisis and Critical Heat Flux,” TID-25887 (1972).
  • D. C. GROENEVELD, K. JOOBER, S. DOERFFER, W. WONG, L. K. H. LEUNG, and S. C. CHENG, “The Effect of Fuel Subchannel Geometry on CHF,” Proc. 5th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-5), Salt Lake City, Utah, September 21–24, 1992, p. 683 (1992).
  • Y. J. YOO, D. H. HWANG, and D. S. SOHN, “Development of a Subchannel Analysis Code MATRA Applicable to PWRs and ALWRs,” J. Korean Nucl. Soc., 31, 314 (1999).
  • D. H. HWANG, Y. J. YOO, W. K. IN, and S. Q. ZEE, “Assessment of the Interchannel Mixing Model with a Subchannel Analysis Code for BWR and PWR Conditions,” Nucl. Eng. Des., 199, 257 (2000).
  • D. H. HWANG, S. Q. ZEE, and M. H. CHANG, “Assessment of CHF Data Base for Square and Non-Square Lattice Rod Bundles,” Proc. Korean Nucl. Soc., Suwon, Korea, October 25–26 2001, (2001) (in Korean).
  • F. INASAKA and H. NARIAI, “Evaluation of Subcooled Critical Heat Flux Correlations for Tubes With and Without Internal Twisted Tapes,” Nucl. Eng. Des., 163, 225 (1996).
  • R. PERNICA and J. CIZEK, “PI Correlations for Prediction of Critical Heat Flux in LWR Fuel Assemblies,” Proc. 5th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-5), Salt Lake City, Utah, September 21–24, 1992, p. 227 (1992).
  • D. H. HWANG, Y. J. YOO, J. R. PARK, and Y. J. KIM, “Evaluation of the Thermal Margin in a KOFA-Loaded Core by a Multichannel Analysis Methodology,” J. Korean Nucl. Soc., 27, 518 (1995).
  • G. ULRYCH, “Application of Tube Critical Heat Flux Tables to Annuli and Rod Bundles,” Proc. 3rd Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-3), Newport, Rhode Island, paper 18.G (1985).
  • T. H. CHUN, D. H. HWANG, W. P. BAEK, and S. H. CHANG, “Assessment of a Tube-Based Bundle CHF Prediction Method Using a Subchannel Code,” Ann. Nucl. Energy, 25, 1159 (1998).
  • D. C. GROENEVELD et al., “A General Method of Predicting Critical Heat Flux in Advanced Water-Cooled Reactors,” Proc. 9th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-9), San Francisco, California, October 3–8, 1999, K.3 (1999).
  • M. M. SHAH, “Improved General Correlation for Critical Heat Flux During Upflow in Uniformly Heated Vertical Tubes,” Heat Fluid Flow, 8, 326 (1987).
  • Y. KATTO and H. OHNO, “An Improved Version of the Generalized Correlation of Critical Heat Flux for the Forced Convective Boiling in Uniformly Heated Vertical Tubes,” Int. J. Heat Mass Transfer, 27, 1641 (1984).
  • D. H. HWANG, C. PARK, and S. Q. ZEE, “A Phenomenological Approach to Correcting DNB-Type Critical Heat Flux for Non-Uniform Axial Power Shapes,” Int. J. Heat Mass Transfer, 44, 4483 (2001).

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