Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Development of a prediction model relating the two-phase pressure drop in a moisture separator using an air/water test facility

  • Kim, Kihwan (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Lee, Jae bong (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Woo-Shik (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Choi, Hae-seob (Innovative System Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Jong-In (Nuclear Power Plant BG, Doosan Heavy Industries & Construction)
  • Received : 2021.03.19
  • Accepted : 2021.06.05
  • Published : 2021.12.25
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Abstract

The pressure drop of a moisture separator in a steam generator is the important design parameter to ensure the successful performance of a nuclear power plant. The moisture separators have a wide range of operating conditions based on the arrangement of them. The prediction of the pressure drop in a moisture separator is challenging due to the complexity of the multi-dimensional two-phase vortex flow. In this study, the moisture separator test facility using the air/water two-phase flow was used to predict the pressure drop of a moisture separator in a Korean OPR-1000 reactor. The prototypical steam/water two-phase flow conditions in a steam generator were simulated as air/water two-phase flow conditions by preserving the centrifugal force and vapor quality. A series of experiments were carried out to investigate the effect of hydraulic characteristics such as the quality and liquid mass flux on the two-phase pressure drop. A new prediction model based on the scaling law was suggested and validated experimentally using the full and half scale of separators. The suggested prediction model showed good agreement with the steam/water experimental results, and it can be extended to predict the steam/water two-phase pressure drop for moisture separators.

Keywords

Acknowledgement

This work was supported by the Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korean government (MOTIE) (20181510102390, Localization of Westinghouse Steam Generator Submerged Separator).

References

  1. U. S. NRC, Steam Separator Modelling for Various Nuclear Reactor Transients, NUREG/CR-4922, 1987. EPRI NP-5272.
  2. S.J. Green, G. Hestroni, PWR steam generators, Int. J. Multiphas. Flow 21 (1995) 1-97.
  3. K. Katono, N. Ishida, T. Sumikawa, K. Yasuda, Air-water downscaled experiments and three-dimensional two-phase flow simulations of improved steam separator for boiling water reactor, Nucl. Eng. Des. 278 (2014) 465-471. https://doi.org/10.1016/j.nucengdes.2014.08.006
  4. K. Kim, W. Kim, J. Lee, D.J. Euh, H.S. Choi, W.J. Jeon, Y.C. Shin, An air/water experimental study on the moisture carry over for the moisture separator of a steam generator, KSFM Journal of Fluid Machinery 23 (2020) 10-17. https://doi.org/10.5293/kfma.2020.23.6.010
  5. G. Mauro, M. Sala, G. Hetsroni, Improved Italian moisture separators (IIMS), Nucl. Eng. Des. 118 (1990) 179-192. https://doi.org/10.1016/0029-5493(90)90056-4
  6. F.T. Sun, et al., The investigation on performance of steam generator stationary vane separator, Chinese Journal of Nuclear Science and Engineering 15 (3) (1994) 213-219.
  7. L. Liu, B. Bai, Scaling laws for gas-liquid flow in swirl vane separators, Nucl. Eng. Des. 298 (2016) 229-239. https://doi.org/10.1016/j.nucengdes.2016.01.001
  8. J.I. Kim, M.Y. Kim, H.S. Bae, B.E. Lee, An experimental investigation for the moisture separation system of a steam generator for nuclear power generation, Proceedings of ICAPP, Reno, USA, 2006. June 4-8, Paper 6103.
  9. G.B. Wallis, One-dimensional Two-phase Flow, McGraw-Hill, 1969.
  10. A.C. Hoffmann, L.E. Stein, Gas Cyclones and Swirl Tubes, Springer, 2007.
  11. I. Kataoka, M. Ishii, Drift-flux model for large diameter pipe and new correlation for pool void fraction, Int. J. Heat Mass Tran. 30 (1987) 1927-1939. https://doi.org/10.1016/0017-9310(87)90251-1
  12. J.P. Schlegel, P. Sawant, S. Paranjape, B. Ozar, T. Hibiki, M. Ishii, Void fraction and flow regime in adiabatic upward two-phase flow in large diameter vertical pipe, Nucl. Eng. Des. 239 (2009) 2864-2874. https://doi.org/10.1016/j.nucengdes.2009.08.004
  13. J.P. Schlegel, S. Miwa, S. Chen, T. Hibiki, M. Ishii, Experimental study of two-phase flow structure in large diameter pipes, Exp. Therm. Fluid Sci. 41 (2012) 12-22. https://doi.org/10.1016/j.expthermflusci.2012.01.034
  14. P. Sawant, M. Ishii, M. Mori, Droplet entrainment correlation in vertical upward co-current annular two-phase flow, Nucl. Eng. Des. 238 (2008) 1342-1352. https://doi.org/10.1016/j.nucengdes.2007.10.005