Home Technology Analytical study of flow instability behaviour in a boiling two-phase natural circulation loop under low quality conditions
Article
Licensed
Unlicensed Requires Authentication

Analytical study of flow instability behaviour in a boiling two-phase natural circulation loop under low quality conditions

  • A. K. Nayak , N. Kumar , P. K. Vijayan , D. Saha and R. K. Sinha
Published/Copyright: March 17, 2022
Become an author with De Gruyter Brill

Abstract

Analytical investigations have been carried out to study the flow instability behaviour in a boiling two-phase natural circulation loop under low quality conditions. For this purpose, the computer code TINFLO-S has been developed. The code solves the conservation equations of mass, momentum and energy and equation of state for homogeneous equilibrium two-phase flow using linear analytical technique. The results of the code have been validated with the experimental data of the loop for both the steady state and stability. The study reveals that the stability behaviour of low quality flow oscillations is different from that of the high quality flow oscillations. The instability reduces with increase in power and throttling at the inlet of the heater. The instability first increases and then reduces with increase in pressure at any subcooling. The effects of diameter of riser pipe, heater and the height of the riser on this instability are also investigated.

Abstract

Das Strömungsverhalten einer siedenden Zweiphasenströmung in einer Schleife mit Naturumlauf unter Bedingungen niedriger Qualität wurde analytisch untersucht. Dazu wurde der Computer-Code TINFLO-S entwickelt. Der Code löst die Erhaltungsgleichungen von Masse, Implus und Energie sowie die Zustandsgleichung für eine Zweiphasenströmung im homogenen Gleichgewicht mit Hilfe linearer analytischer Verfahren. Die Studie zeigt, dass das Stabilitätsverhalten von Strömungsoszillationen niedriger Qualität verschieden ist von dem Verhalten bei hoher Qualität. Die Instabilität verringert sich mit einer Erhöhung der Leistung am Eingang der heißen Zone. Die Instabilität erhöht sich zuerst und erniedrigt sich dann mit steigendem Druck bei jeder Unterkühlung. Der Einfluss von Durchmesser und Höhe des Steigrohres, sowie der heißen Zone auf die Instabilität wurde ebenfalls untersucht.

Nomenclature

A

cross-sectional area (m2)

Cp

specific heat (J/kg K)

D

hydraulic diameter (m)

f

Darcy friction factor

g

acceleration due to gravity (m/s2)

h

specific enthalpy (J/kg)

hfg

latent heat of vaporisation (J/kg)

L

length of section (m)

p

pressure (N/m2)

Δp

pressure drop (N/m2)

qh

heat applied/unit volume of coolant (W/m3)

s

growth rate of perturbations time (s)

T

temperature (K)

Tsat

saturation temperature (K)

v

specific volume (m3/kg)

w

mass flow rate (kg/s)

x

axial distance (m)

Greek symbols

σ

volumetric thermal expansion coefficient (K–1)

μ

dynamic viscosity (N s/m2)

ρ

density (kg/m3)

τ

residence time of fluid (s)

Δ

Difference

Subscripts

av

average

c

channel

d

downcomer

f

saturated liquid

g

saturated vapour

in

inlet of section

L

over section length

ss

steady state

ss,av

average steady state

vfg

(vgvf) (m3/kg)

References

1 Duncan, J. D.: SBWR-Simplified Boiling Water Reactor. Nuclear Engineering and Design 10 (1988) 7710.1016/0029-5493(88)90143-4Search in Google Scholar

2 Sinha, R. K.; Kakodkar, A.: Requirements for the design of the Advanced Heavy Water Reactor. IAEA TCM workshop for next generation water cooled reactors, Beijing, China, October, 1990Search in Google Scholar

3 Boure, J. A.; Bergles, A. E.; Tong, L. S.: Review of two-phase flow instability. Nuclear Engineering and Design 25 (1973) 16510.1016/0029-5493(73)90043-5Search in Google Scholar

4 Fukuda, K.; Kobori, T.: Classification of two-phase flow stability by density-wave oscillation model. Journal of Nuclear Science and Technology 16 (1979) 9510.1080/18811248.1979.9730878Search in Google Scholar

5 Takitani, K.; Takemura, T.: Density-wave oscillations in once through boiling system. Journal of Nuclear Science and Technology 15 (1978) 35510.1080/18811248.1978.9735521Search in Google Scholar

6 Nakanishi, S.; Ishigai, S.; Ozawa, M.; Mizuta, Y.; Tarui, H.: Flow instabilities in boiling channels; density-wave oscillation in a single channel boiling system. Theoretical and Applied Mechanics 26 (1978) 421Search in Google Scholar

7 Wang, Q.; Chen, X. J.; Kakac, S.; Ding, Y.: An experimental investigation of density-wave type oscillations in a convective boiling up-flow system. International Journal of Multiphase Flow 15 (1994) 24110.1016/0142-727X(94)90044-2Search in Google Scholar

8 Xiao, M.; Chen, X. J.; Zhang, M. Y.; Veziroglu, T. N.; Kakac, S.: A multivaraible linear investigation of two-phase flow instabilities in parallel boiling channels under high pressure. International Journal of Multiphase Flow 19 (1993) 6510.1016/0301-9322(93)90023-NSearch in Google Scholar

9 Aritomi, M.; Chiang, J. H.; Nakahashi, T. M.; Wataru, M.; Mori, M.: Fundamental study on thermohydraulics during start-up in a natural circulation Boiling Water Reactor (I), Thermohydraulic Instabilities. Journal of Nuclear Science and Technology 29 (1992) 63110.1080/18811248.1992.9731576Search in Google Scholar

10 Lee, S. Y.; Ishii, M.: Characteristics of two-phase natural circulation in Freon-113 boiling loop. Nuclear Engineering and Design 121 (1990) 6910.1016/0029-5493(90)90009-MSearch in Google Scholar

11 Kyung, L. S.; Lee, S. Y.: Experimental observations in an open two-phase natural circulation loop. Nuclear Engineering and Design 159 ( 1994) 16310.1016/0029-5493(94)90060-4Search in Google Scholar

12 Wu, C. Y.;Wang, S. B.; Pan, C.: Chaotic oscillations in a low pressure two-phase natural circulation loop. Nuclear Engineering and Design 162 (1996) 22310.1016/0029-5493(95)01127-7Search in Google Scholar

13 Jiang, S. Y.; Yao, M. S.; Bo, J. H.;Wu, S. R.: Experimental simulation study on start-up of the 5 MW nuclear heating reactor. Nuclear Engineering and Design 158 (1995) 11110.1016/0029-5493(95)01020-ISearch in Google Scholar

14 Nayak, A. K.; Vijayan, P. K.; Saha, D.: Analytical Modelling and Study of the stability characteristics of the Advanced Heavy water Reactor. BARC Report No. BARC/2000/E/O 11Search in Google Scholar

15 Owens, W. S.: Two-phase pressure gradient. Inernational. Developments in Heat Transfer, Part II, ASME (1961)Search in Google Scholar

16 Kumar, N.; Nayak, A. K.; Vijayan, P. K.; Saha, D.: Experimental investigations on two-phase natural circulation in a closed rectangular loop. 2nd Japan-Korea Seminar on Nuclear Thermalhydraulics and Safety, October 15–18, Fukuoka, Japan (2000)Search in Google Scholar

17 Lockhart, R. W.; Martinelli, R. C.: Proposed correlation of data for isothermal two-phase, two component flow in pipes. Chemical Engineering Progress, 45 (1949) 39Search in Google Scholar

18 Martinelli, R. C.; Nelson, D. B.: Prediction of pressure drop during forced circulation boiling of water. Transactions of ASME 70 (1984) 69510.1115/1.4017819Search in Google Scholar

19 Chisholm, D., Laird, A. D.: Two-phase flow in rough tubes. Transactions of ASME 80 (1958) 27610.1115/1.4012342Search in Google Scholar

20 Sekoguchi, K.; Sato, Y.; Honda, T.: JSME Preprint No. 700-7, 83 (1970)Search in Google Scholar

Received: 2002-01-16
Published Online: 2022-03-17

© 2002 Carl Hanser Verlag, München

Articles in the same Issue

  1. Frontmatter
  2. Calendar of Events
  3. Calendar of events . Veranstaltungskalender
  4. Summaries
  5. Summaries
  6. Books
  7. Safety Assessment and Verification for Nuclear Power Plants
  8. 3D numerical investigation of natural circulation between the reactor pressure vessel and the cooling pond of a VVER-440 type reactor in incidental conditions during maintenance
  9. A process-oriented simulation model for common cause failures
  10. Books
  11. Books · Bücher
  12. Simulation of pulsed neutron activation for determination of water flow in pipes
  13. Books
  14. Books · Bücher
  15. Adjoint P1 equations for neutron slowing down
  16. Books
  17. Bücher · Books
  18. Experimental and numerical investigation of sub-cooled boiling, condensation, and void flashing in nuclear heating reactor test loop
  19. Analytical study of flow instability behaviour in a boiling two-phase natural circulation loop under low quality conditions
  20. Books
  21. Bücher · Books
  22. Thermal hydraulic analysis and design of the WWR-M2 nuclear research reactor – power upgrading
  23. Books
  24. Books · Bücher
  25. Simulation of the gamma dose rate in a loss of pool water accident of the second Egyptian research reactor ET-RR-2
  26. Behaviour of electrical cables under fire conditions
  27. Books
  28. Better integration of radiation protection in modern society.
  29. Berechnungsverfahren für Temperaturen im Brandnahbereich
  30. Books
  31. Modifications to Nuclear Power Plants
  32. Alerting procedures for scenarios without warning times
  33. Technical Note
  34. Approximation of solitary burn-up waves by generalized Gompertz functions
  35. Advances · Patente
  36. Patent
  37. Note · Mitteilung
  38. Notes
Downloaded on 11.12.2025 from https://www.degruyterbrill.com/document/doi/10.1515/kern-2002-0042/pdf
Scroll to top button