Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지

Application of the Through-Transmitted Ultrasonic Signal for the Identification of Two-Phase Flow Patterns in a Simulated High Temperature Vertical Channel

  • Published : 2004.02.01
Download PDF
⟨ Previous Next ⟩

Abstract

In the present study a new measurement technique has been developed, which uses an ultrasonic transmission signal in order to identify the vertical two phase flow pattern. The ultrasonic measurement system developed in the present study not only provides the information required for the identification of vertical two phase flow patterns but also makes real time identification possible. Various vertical two phase flow patterns such as bubbly, slug, churn, annular flow etc. have been accurately identified with the present ultrasonic measurement system under atmospheric condition. In addition, the present test apparatus can practically simulate the ultrasonic propagation characteristics under high temperature and high pressure systems. Therefore, it is expected that the present ultrasonic flow pattern identification technique could be applicable to the vertical two phase flow systems under high temperature and high pressure conditions.

Keywords

References

  1. N.K. Tutu, 'Pressure Fluctuations and Flow Pattern Recognition in Vertical Two-Phase Gas-Liquid Flows,' International Journal of Multiphase Flow, 8, 443 (1982) https://doi.org/10.1016/0301-9322(82)90053-2
  2. Jones, O.C. and Zuber, N., 1975, 'The Interrelation Between Void Fraction Fluctuations and Flow Pattern in Two-Phase Flow,' Int. J. Multiphase Flow, Vol. 2, pp. 273-306 https://doi.org/10.1016/0301-9322(75)90015-4
  3. R.E. Haberstrah and P. Griffith, 'The Slug-Annular Two-Phase Flow Regime Transition,' ASME Paper No. 65-HT-52 (1965)
  4. C.-H. Song and M.K. Chung, 'Development of the Impedance Void Meter,' KAERI/TR-446/94, KAERI Technical Report (1994)
  5. C.-H. Song, H.C. No, and M.K. Chung, 'Investigation of Bubble Flow Developments and Its Transition Based on the Instability of Void Fraction Waves,' International Journal of Multiphase Flow, 21, 381 (1995) https://doi.org/10.1016/0301-9322(94)00079-Y
  6. Song C.-H. Song, M.K. Chung, and H.C. No, 'Measurement of Void Fraction by an Improved Multi-Channel Conductance Void Meter,' Nuclear Engineering and Design, 184, 269 (1998) https://doi.org/10.1016/S0029-5493(98)00202-7
  7. J.S. Chang and E.C. Morala, 'Determination of Two-Phase Interfacial Areas by an Ultrasonic Technique,' Nuclear Engineering and Design, 122, 143 (1990) https://doi.org/10.1016/0029-5493(90)90203-A
  8. I.-C. Chu and C.-H Song, 'Identification of Vertical Two-Phase Flow Pattern Using Ultrasonic Thru. Transmission Technique,' NTHAS3: Third Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 226, Kyeongju, Korea, October 13-16 (2002)