Table of Contents Author Guidelines Submit a Manuscript
Science and Technology of Nuclear Installations
Volume 2012 (2012), Article ID 174838, 7 pages
http://dx.doi.org/10.1155/2012/174838
Research Article

Countercurrent Air-Water Flow in a Scale-Down Model of a Pressurizer Surge Line

1Department of Mechanical Engineering, Faculty of Engineering, Kobe University, 1-1 Rokkodai, Nada, Hyogo Kobe, 657-8501, Japan
2Institute of Nuclear Safety System, Inc. (INSS), 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan

Received 13 October 2011; Accepted 16 December 2011

Academic Editor: Thomas Hoehne

Copyright © 2012 Takashi Futatsugi 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. N. Minami, D. Kataoka, A. Tomiyama, S. Hosokawa, and M. Murase, “Countercurrent gas-liquid flow in a rectangular channel simulating a PWR hot leg (1) flow pattern and CCFL characteristics,” Japanese Journal of Multiphase Flow, vol. 22, no. 4, pp. 403–412, 2008 (Japanese). View at Google Scholar
  2. N. Minami, M. Murase, D. Nishiwaki, and A. Tomiyama, “Countercurrent gas-liquid flow in a rectangular channel simulating a PWR hot leg (2) analytical evaluation of countercurrent flow limitation,” Japanese Journal of Multiphase Flow, vol. 22, no. 4, pp. 413–422, 2008 (Japanese). View at Google Scholar
  3. H. Nakamura, J. Katayama, and Y. Kukita, “Loss of residual heat removal (RHR) event during PWR mid-loop operation: ROSA-IV/LSTF experiment without opening on primary loop pressure boundary,” American Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED, vol. 140, pp. 9–16, 1992. View at Google Scholar
  4. K. Takeuchi, M. Y. Young, and A. F. Gagnon, “Flooding in the pressurizer surge line of AP600 plant and analyses of APEX data,” Nuclear Engineering and Design, vol. 192, no. 1, pp. 45–58, 1999. View at Publisher · View at Google Scholar · View at Scopus
  5. L. E. Hochreiter, S. V. Fanto, L. E. Conway, and L. K. Lau, “Integral testing of the AP600 passive emergency core cooling systems,” Journal of Power and Energy, vol. 207, no. 4, pp. 259–268, 1993. View at Google Scholar
  6. J. N. Reyes, “Scaling Analysis for the OSU AP600 Integral Systems and Long Term Cooling Facility,” OSU-NE-9204, 1992.
  7. G. B. Wallis, One Dimensional Two-Phase Flow, McGraw Hill, New York, NY, USA, 1969.
  8. S. Levy, Two-Phase Flow in Complex Systems, Wiley Interscience, 1999.
  9. G. F. Hewitt and G. B. Wallis, ASME Multi-Phase Flow Symposium, ASME, Philadelphia, Pa, USA, 1963.
  10. N. Minami, D. Nishiwaki, T. Nariai, A. Tomiyama, and M. Murase, “Countercurrent gas-liquid flow in a PWR hot leg under reflux cooling (I) air-water tests for 1/15-scale model of a PWR hot leg,” Journal of Nuclear Science and Technology, vol. 47, no. 2, pp. 142–148, 2010. View at Publisher · View at Google Scholar · View at Scopus
  11. H. J. Richter, G. B. Wallis, K. H. Carter et al., “Deentrainment and Countercurrent Air-Water Flow in a Model PWR Hot-Leg,” NRC-0193-9, U.S. Nuclear Regulatory Commission, 1978.
  12. A. Ohnuki, “Experimental study of counter-current two-phase flow in horizontal tube connected to an inclined riser,” Journal of Nuclear Science and Technology, vol. 23, no. 3, pp. 219–232, 1986. View at Google Scholar · View at Scopus
  13. A. Ohnuki, H. Adachi, and Y. Murao, “Scale effects on countercurrent gas-liquid flow in a horizontal tube connected to an inclined riser,” Nuclear Engineering and Design, vol. 107, no. 3, pp. 283–294, 1988. View at Google Scholar · View at Scopus
  14. F. Mayinger, P. Weiss, and K. Wolfert, “Two-phase flow phenomena in full-scale reactor geometry,” Nuclear Engineering and Design, vol. 145, no. 1-2, pp. 47–61, 1993. View at Google Scholar · View at Scopus
  15. P. B. Whalley, Boiling Condensation and Gas-Liquid Flow, Oxford University Press, New York, NY, USA, 1987.
  16. J. M. Delhaye, M. Giot, and M. L. Riethmuller, Thermohydraulics of Two-Phase Systems for Industrial Design and Nuclear Engineering, Hemisphere, New York, NY, USA, 1981.