Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

A SIMPLE ANALYTICAL METHOD FOR NONLINEAR DENSITY WAVE TWO-PHASE INSTABILITY IN A SODIUM-HEATED AND HELICALLY COILED STEAM GENERATOR

  • Kim, Seong-O (Korea Atomic Energy Research Institute, Fast Reactor Development Division) ;
  • Choi, Seok-Ki (Korea Atomic Energy Research Institute, Fast Reactor Development Division) ;
  • Kang, Han-Ok (Korea Atomic Energy Research Institute, Fast Reactor Development Division)
  • Published : 2009.08.31
Download PDF
⟨ Previous Next ⟩

Abstract

A simple model to analyze non-linear density-wave instability in a sodium-cooled helically coiled steam generator is developed. The model is formulated with three regions with moving boundaries. The homogeneous equilibrium flow model is used for the two-phase region and the shell-side energy conservation is also considered for the heat flux variation in each region. The proposed model is applied to the analysis of two-phase instability in a JAEA (Japan Atomic Energy Agency) 50MWt No.2 steam generator. The steady state results show that the proposed model accurately predicts the six cases of operating temperatures on the primary and secondary sides. The sizes of three regions, the secondary side pressure drop according to the flow rate, and the temperature variation in the vertical direction are also predicted well. The temporal variations of the inlet flow rate according to the throttling coefficient, the boiling and superheating boundaries and the pressure drop in the two-phase and superheating regions are obtained from the unsteady analysis.

Keywords

References

  1. S. Kakac, and H. T. Liu, “Two-Phase Flow Dynamic Instabilities in Boiling System,” Multiphase Flow and Heat Transfer, pp.403-444, (1991)
  2. J. A. Boure, A. E. Bergles and L. S. Tong, “Review of Two-Phase Flow Instability,” Nuclear Engineering and Design, Vol.25, pp. 165-192, (1973) https://doi.org/10.1016/0029-5493(73)90043-5
  3. R. P. Waszink, and L. E. Efferding, “Hydrodynamic Stability and Thermal Performance Test of a 1-MWt Sodium Heated Once-Through Steam Generator Model,” ASME paper 73- PWR-16 (1973)
  4. H. C. Unal, M. L. G. van Gasselt, and P. W. P. H. Ludwig, "Dynamic Instabilities in Tubes of a Large Capacity, Straight-Tube, Once-Through Sodium Heated Steam Generator," Int. J. Heat Mass Transfer, Vol. 20, pp.1389-1398, (1977) https://doi.org/10.1016/0017-9310(77)90036-9
  5. H. C. Unal, “Correlations for the Determination of the Inception Conditions of Density-Wave Oscillations for Forced and Natural Circulation Steam Generator Tubes, Trans. ASME J. Heat Transfer, Vol. 102, pp. 14-19, (1980) https://doi.org/10.1115/1.3244227
  6. H. C. Unal, “Density-Wave Oscillations in Sodium Heated Once-Through Steam Generator Tubes,” Trans. ASME J. Heat Transfer, Vol. 103, pp. 485-491 https://doi.org/10.1115/1.3244490
  7. A. Sano, A. Kanamori, T. Tsuchiya and H. Yamashita, “1- MWt Steam Generator Operating Experience,” ASMEpaper 73-HT-53, (1973)
  8. T. Tsuchiya, J. Kubota, T. Takeuchi and T. Takemura, “Hydrodynamic Stability Tests for LMFBR Sodium Heated Steam Generators,” Proceedings of Japan-US Seminar on Two-Phase Flow Dynamics, pp. 399-414, (1979)
  9. J. Kubota and T. Tsuchiya, “Hydrodynamic Stability Tests and Analytical Model Development for Once-Through Sodium Heated Steam Generator,” Boiler Dynamic and Control in Nuclear Power Stations, pp. 105-115, (1979)
  10. F. Manabe, T. Kosugi, T. Tsuchiya and J. Endo, “Experimental Studies of Heat Transfer Performance with the NO.2 50MW Steam Generator in Japan,” The Topical Meeting on R&D Fabrication and Operating Experience on Steam Generators for LMFBR's, (1981)
  11. H. O. Kang et al., Analysis of Once-Through Steam Generator Instability, KAERI Report, KAERI/TR-1068, (1998)
  12. S. Kalish, and O. E. Dwyer, “Heat Transfer to NaK Flow through Unbaffled Rod Bundle,” Int. J. Heat and Mass Transfer, Vol.10, pp. 1533-1558, (1967) https://doi.org/10.1016/0017-9310(67)90006-3
  13. Y. Mori, and W. Nakayama, “Study on Forced Convective Heat Transfer in Curved Pipes,” Int. J. Heat and Mass Transfer, Vol.10, pp.37-59, (1967) https://doi.org/10.1016/0017-9310(67)90182-2
  14. V. E. Schrock and L. F. Grossman, Forced Convection Boiling Studies, The University of California Berkeley, Report no.73308-UCX-2182, (1959)
  15. H. Ito, "Friction Factors for Turbulent Flow in Curved Pipes," Trans. ASME J. Basic Eng. Vol. 81, pp. 123-134, (1959)
  16. M. Kozeki, H. Nariai, T. Furukawa and K. Kurosu, “A Study of Helically-Coiled Tube Once-Through Steam Generator,” Bulletin of the JSME, Vol.13, pp. 1485-1494, (1970) https://doi.org/10.1299/jsme1958.13.1485
  17. H. K. Kang, H. Y. Kim, J. H. Yoon, J. P. Kim and D. J. Lee, “Development of Simple Analytical Model for Helical Once Through Steam Generator Instability,' Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9), San Francisco, California, October 3-8, (1999).
  18. H. Nariai , “Friction Pressure Drop and Heat Transfer Coefficient of Two-Phase Flow in the Helically Coiled Tube Once-Through Steam Generator for Integrated Type Marine Water Reactor, J. Nuc. Sci. Tec. Vol.19(11), pp. 936~947, 1982 https://doi.org/10.3327/jnst.19.936