Analytical study of flow instability behaviour in a boiling two-phase natural circulation loop under low quality conditions
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A. K. Nayak
, N. Kumar , P. K. Vijayan , D. Saha and R. K. Sinha
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
(vg – vf) (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
© 2002 Carl Hanser Verlag, München
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Articles in the same Issue
- Frontmatter
- Calendar of Events
- Calendar of events . Veranstaltungskalender
- Summaries
- Summaries
- Books
- Safety Assessment and Verification for Nuclear Power Plants
- 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
- A process-oriented simulation model for common cause failures
- Books
- Books · Bücher
- Simulation of pulsed neutron activation for determination of water flow in pipes
- Books
- Books · Bücher
- Adjoint P1 equations for neutron slowing down
- Books
- Bücher · Books
- Experimental and numerical investigation of sub-cooled boiling, condensation, and void flashing in nuclear heating reactor test loop
- Analytical study of flow instability behaviour in a boiling two-phase natural circulation loop under low quality conditions
- Books
- Bücher · Books
- Thermal hydraulic analysis and design of the WWR-M2 nuclear research reactor – power upgrading
- Books
- Books · Bücher
- Simulation of the gamma dose rate in a loss of pool water accident of the second Egyptian research reactor ET-RR-2
- Behaviour of electrical cables under fire conditions
- Books
- Better integration of radiation protection in modern society.
- Berechnungsverfahren für Temperaturen im Brandnahbereich
- Books
- Modifications to Nuclear Power Plants
- Alerting procedures for scenarios without warning times
- Technical Note
- Approximation of solitary burn-up waves by generalized Gompertz functions
- Advances · Patente
- Patent
- Note · Mitteilung
- Notes