Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2012, Article ID 746467, 20 pages
http://dx.doi.org/10.1155/2012/746467
Research Article

Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes

1Nuclear Energy and Safety Research Department, Paul Scherrer Institute, 5232 Villigen, Switzerland
2Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan 689-882, Republic of Korea
3Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, MI 48109, USA
4CD-adapco, Trident House, Basil Hill Road, Didcot OX11 7HJ, UK

Received 30 April 2012; Accepted 20 July 2012

Academic Editor: David Novog

Copyright © 2012 Taewan Kim et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. B. Neykov, A. Aydogan, L. Hochreiter et al., “NUPEC BWR full-size fine-mesh bundle test (BFBT) Benchmark, volume I: specifications,” NEA/NSC/DOC(2005)5, 2006.
  2. A. Rubin, A. Schoedel, M. Avramova, H. Utsuno, S. Bajorek, and A. Velazquez-Lozada, “OECD/NRC benchmark based on NUPEC PWR subchannel and bundle tests (PSBT), volume I: experimental database and final problem specifications,” NEA/NSC/DOC(2010)1, 2010.
  3. I. Toumi, A. Bergeron, D. Gallo, E. Royer, and D. Caruge, “FLICA-4: a three-dimensional two-phase flow computer code with advanced numerical methods for nuclear applications,” Nuclear Engineering and Design, vol. 200, no. 1, pp. 139–155, 2000. View at Publisher · View at Google Scholar · View at Scopus
  4. CD-adapco, CCM User Guide: STAR-CD Version 4.06, 2008.
  5. US NRC, TRACE V5.0 Theory Manual: Field Equations, Solution Methods, and Physical Models, U.S. Nuclear Regulatory Commission, Washington, DC, USA, 2009.
  6. B. Chexal, G. Lellouche, J. Horowitz, and J. Healzer, “A void fraction correlation for generalized applications,” Progress in Nuclear Energy, vol. 27, no. 4, pp. 255–295, 1992. View at Google Scholar · View at Scopus
  7. T. Kim, “Collaboration with CEA saclay for OECD-NEA PSBT benchmark—single channel benchmark with FLICA4,” PSI Memorandum SB-RND-ACT-003-10.002, 2010. View at Google Scholar
  8. F. W. Dittus and L. M. K. Boelter, “Heat transfer in automobile radiators of the tubular type,” University of California Publications in Engineering, vol. 2, no. 13, pp. 443–461, 1930, Reprinted in International Communications in Heat and Mass Transfer, vol. 12, pp. 3-22, 1985. View at Google Scholar · View at Scopus
  9. CEA, FLICA4 User Guide – Reference Manual of Modules and Procedures, 2009.
  10. P. Raymond, B. Spindler, and R. Lenain, “Pressurized water reactor thermal-hydraulic core analysis with the FLICA computer code,” Nuclear Engineering and Design, vol. 124, no. 3, pp. 299–313, 1990. View at Google Scholar · View at Scopus
  11. F. P. Incropera and D. P. Dewitt, Introduction to Heat Transfer, John Willey & Sons, New York, NY, USA, 3rd edition, 1996.
  12. L. Friedel, “Improved friction pressure drop correlations for horizontal and vertical two phase pipe flow,” in Proceedings of the European Two Phase Flow Group Meeting, Ispra, Italy, June 1979.
  13. V. Gnielinski, “New equations flow regime heat and mass transfer in turbulent pipe and channel flow,” International Chemical Engineering, vol. 16, pp. 359–368, 1976. View at Google Scholar
  14. M. A. Aggour, M. M. Vijay, and G. E. Sims, “A correlation of mean heat transfer coefficients for two-phase two-component flow in a vertical tube,” in Proceedings of the 7th International Heat Transfer Conference, vol. 5, pp. 367–372, 1982.
  15. K. S. Rezkallah and G. E. Sims, “An examination of correlations of mean heat transfer coefficients in two-phase two-component flow in vertical tubes,” AIChE Symposium Series, vol. 83, no. 257, pp. 109–114, 1987. View at Google Scholar
  16. R. T. Lahey, “A mechanistic subcooled boiling model,” in Proceedings of the 6th International Heat Transfer Conference, vol. 1, pp. 293–297, Toronto, Canada, 1978.
  17. S. W. Churchill, “Friction factor equations spans all fluid-flow regimes,” Chemical Engineering, vol. 84, no. 24, pp. 91–92, 1977. View at Google Scholar · View at Scopus
  18. E. Ranz and W. R. Marshall, “Evaporation from Droplets: part I and II,” Chemical Engineering Progress, vol. 48, pp. 141–180, 1952. View at Google Scholar
  19. M. Ishii and K. Mishima, “Study of two-fluid model and interfacial area,” Argonne National Laboratory Report ANL-80-111 (NUREG/CR-1873), 1980. View at Google Scholar
  20. R. T. Lahey and F. J. Moody, The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, ANS Monograph, 1977.
  21. D. B. Spalding, “The calculation of free-convection phenomena in gas—liquid mixtures,” in Heat Transfer and Turbulent Buoyant Convection Studies and Applications for Natural Environment, Buildings and Engineering Systems, D. B. Spalding and N. Afgan, Eds., vol. 2, pp. 569–586, Hemisphere, New York, NY, USA, 1976. View at Google Scholar
  22. D. B. Spalding, “Numerical computation of multi-phase fluid flow and heat transfer,” in Recent Advances in Numerical Methods in Fluids, C. Taylor and K. Morgan, Eds., vol. 1, pp. 139–168, Pineridge Press, Swansea, UK, 1980. View at Google Scholar
  23. D. B. Spalding, “Developments in the IPSA procedure for numerical computation of multi-phase flow phenomena with interphase slip, unequal temperatures, etc,” in Numerical Methodologies in Heat Transfer, T. M. Shih, Ed., Proceedings of the Second National Symposium, pp. 421–436, Hemisphere, New York, NY, USA, 1983. View at Google Scholar
  24. N. Kurul and M. Z. Podowski, “Multi-dimensional effects in subcooled boiling,” in Proceedings of the 9th Heat Transfer Conference, Jerusalem, Israel, 1990.
  25. T. Hibiki and M. Ishii, “One-demensional drift-flux model for two-phase flow in a large diameter pipe,” International Journal of Heat and Mass Transfer, vol. 46, no. 10, pp. 1773–1790, 2003. View at Publisher · View at Google Scholar · View at Scopus
  26. G. Kocamustafaogullari, “Pressure dependence of bubble departure diameter for water,” International Communications in Heat and Mass Transfer, vol. 10, no. 6, pp. 501–509, 1983. View at Google Scholar · View at Scopus
  27. L. S. Tong, “Heat transfer in water-cooled nuclear reactors,” Nuclear Engineering and Design, vol. 6, no. 4, pp. 301–324, 1967. View at Google Scholar · View at Scopus
  28. D. C. Groeneveld, L. K. H. Leung, P. L. Kirillov et al., “The 1995 look-up table for critical heat flux in tubes,” Nuclear Engineering and Design, vol. 163, no. 1-2, pp. 1–23, 1996. View at Google Scholar · View at Scopus
  29. A. Rubin, “Comparative analysis of submitted participants’ preliminary results for exercise II-2,” in Proceedings of the 2nd PSBT Workshop, Stockholm, Sweden, April 2011.
  30. A. Rubin, “Comparative analysis of submitted participants’ preliminary results for exercise II-3,” in Proceedings of the 2nd PSBT Workshop, Stockholm, Sweden, April 2011.
  31. Y. Sudo, K. Miyata, H. Ikawa, M. Kaminaga, and M. Ohkawara, “Experimental study of differences in DNB heat flux between upflow and downflow in vertical rectangular channel,” Journal of Nuclear Science and Technology, vol. 22, no. 8, pp. 604–618, 1985. View at Google Scholar · View at Scopus
  32. N. E. Todreas and M. S. Kazimi, Nuclear Systems: Vol. 1, Thermal Hydraulic Fundamentals, Hemisphere, New York, NY, USA, 1990.