Abstract
The implementation of passive safety systems in nuclear reactors provides the opportunity to enhance the nuclear safety. On the other hand, an accurate and reliable prediction of the heat removal behavior is not ensured because the operating conditions of certain types of passive systems like containment cooling systems differ from the validity ranges of the established heat transfer correlations. Therefore, a generic and detailed investigation is still necessary for passive systems.
Against this background, the test facility GENEVA was erected at Technische Universität Dresden in 2012. Since the commissioning, generic experiments concerning the system and stability behavior of this facility, which emulate a low-pressure and low-flow (LPLF) natural circulation system, were provided. Nevertheless, the investigation of the heat transfer behavior remained an open issue. On this account, the instrumentation in the heat transfer region inside GENEVA was improved to gather the necessary temperature and void fraction profiles.
The performed experiments provide a generic and wide database concerning boiling in a LPLF natural circulation systems. Within this paper, the development of the wall and bulk fluid temperature as well as the axial and center line void fraction profile in a slightly inclined tube for different heat flow rates are discussed. Furthermore, flow patterns could be identified on behalf of the void fraction measurements. To conclude the experimental analysis, the development of the heat transfer coefficient was estimated.
These experimental data provide the basis for a simulation with the lumped-parameter thermal-hydraulic code ATHLET and serve as validation reference. However, the comparisons between the experimental and computational results show insufficient agreements. Mainly, the simulation misses the saturation point of the experiments, which leads to great differences of the void fraction values. Moreover, inaccuracies appear as well with the heat transfer coefficient.
The experimental and computational results that are discussed in this paper provide the basis for the advancement not only of heat transfer correlations but also of flow pattern maps within the range of low pressure natural circulation system. In summary, this investigation contributes to the general purpose to enhance nuclear safety by providing an accurate and reliable prediction o f the heat removal capacity of passive systems.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
Change history
05 February 2022
A Correction to this paper has been published: https://doi.org/10.1007/s42757-022-0132-z
References
Beyer, M., Szalinski, L., Schleicher, E., Schunk, C. 2017. Wire-mesh sensor data processing software. User manual and software description.
Bonn, W., Iwicki, J., Krebs, R., Steiner, D., Schlünder, E. U. 1980. Über die Auswirkungen der Ungleichverteilung des Wärmeübergangs Am Rohrumfang bei der Verdampfung im durchströmten waagerechten Rohr. Wärme- Und Stoffübertragung, 13: 265–274.
Buchholz, S., von der Cron, D., Schaffrath, A. 2016. System code improvements for modelling passive safety systems and their validation. Kerntechnik, 81: 535–542.
Chen, J. C. 1966. Correlation for boiling heat transfer to saturated fluids in convective flow. Ind Eng Chem Proc DD, 5: 322–329.
Cloppenborg, T., Schuster, C., Hurtado, A. 2015. Two-phase flow phenomena along an adiabatic riser-An experimental study at the test-facility GENEVA. Int J Multiphase Flow, 72: 112–132.
Dittus, F. W., Boelter, L. M. K. 1985. Heat transfer in automobile radiators of the tubular type. Int Commun Heat Mass, 12: 3–22.
Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH (GRS). 2016a. ATHLET 3.1A. Models and methods.
Gesellschaft für Anlagen- und Reaktorsicherheit gGmbH (GRS). 2016b. ATHLET 3.1A. Validation.
International Atomic Energy Agency. 2009. IAEA-TECDOC-1624. Passive safety systems and natural circulation in water cooled nuclear power plants.
Kays, W. M., Nicoll, W. B. 1963. Laminar flow heat transfer to a gas with large temperature differences. J Heat Transf, 85: 329–338.
McAdams, W. H. 1942. Heat Transmission, 2nd edn. New York and London: McGraw-Hill Book Company Inc.
McEligot, D. M., Swearingen, T. B. 1966. Prediction of wall temperatures for internal laminar heat transfer. Int J Heat Mass Tran, 9: 1151–1152.
Morris, F. H., Whitman, W. G. 1928. Heat transfer for oils and water in pipes. Ind Eng Chem, 20: 234–240.
Prasser, H.-M., Böttger, A., Zschau, J. 1998. A new electrode-mesh tomograph for gas-liquid flows. Flow Meas Instrum, 9: 111–119.
Sani, R. L. 1960. Downflow boiling and nonboiling heat transfer in a uniformly heated tube. Master Thesis. University of California, Berkeley, U.S.A. Lawrence Radiation Laboratory.
Schleicher, E., Bieberle, A., Tschofen, M., Hampel, U., Lineva, N., Maisberger, F., Leyer, S. 2011. Measurement of two-phase flow parameters with multi-channel gamma densitometry and local void probes at the INKA test facility. In: Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14-354, 25–30.
Schöffel, P., Ceuca, S., Deitenbeck, H., Kloos, M., Langenfeld, A., Lerchl, G. 2015. Weiterentwicklung des Systemrechenprogramms ATHLET für Anwendungen in der Reaktorsicherheit. Im Rahmen des EU-Projekts THINS: Abschlussbericht. Köln (GRS).
Schrock, V. E., Grossman, L. M. 1962. Forced convection boiling in tubes. Nucl Sci Eng, 12: 474–481.
Steiner, D. 2006. Strömungssieden gesättigter Flüssigkeiten. In Verein Deutscher Ingenieure, VDI-Gesellschaft Verfahrenstechnik und Chemie-ingenieurwesen (Eds.): VDI-Wärmeatlas, 10th edn. Berlin, Heidelberg: Springer Verlag Berlin Heidelberg, Hbb1–Hbb35.
Wright, R. M. 1961. Downflow forced-convection boiling of water in uniformly heated tubes. Dissertation. University of California, Berkeley, U.S.A. Lawrence Radiation Laboratory.
Acknowledgements
This work is part of the research project “PANAS” and is funded by the German Federal Ministry of Education and Research (BMBF) under the contract number 02NUK041A. Responsibility for the content of this publication lies with the authors.
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Viereckl, F., Schleicher, E., Schuster, C. et al. Experimental and theoretical investigation of the boiling heat transfer in a low-pressure natural circulation system. Exp. Comput. Multiph. Flow 1, 286–299 (2019). https://doi.org/10.1007/s42757-019-0023-0
Received:
Revised:
Accepted:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s42757-019-0023-0