Analytical study of the closure flow inside the ETRR-2 core chimney
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S. El-Din El-Morshdy
Abstract
The present work is carried out in order to study the closure flow inside the core chimney of the Egypt Second Research Reactor (ETRR-2). Based on the finite difference technique, a two dimensional model is developed to simulate the coolant flow inside the chimney. The model is verified by FEHT finite element program. Then a study of different closure flow values inside the chimney was made using the developed model where a flow map is plotted showing the stagnation depth for each closure flow. The flow map shows that for a closure flow greater than 0.16 m3/h, no active water ascends from the core to the pool through the chimney. The model results are analyzed and discussed.
Kurzfassung
In der vorliegenden Arbeit wurde die Einschluss-Strömung (closure flow) innerhalb des Kern-Kamins des zweiten ägyptischen Forschungsreaktors (ETRR-2) untersucht. Auf der Grundlage der Finite-Differenzen Methode wurde ein zweidimensionales Modell entwickelt, um den Kühlmittelfluss innerhalb des Kamins zu simulieren. Das Modell wurde verifiziert mit Hilfe des FEHT Finite-Elemente-Programms. Danach wurde mit Hilfe des entwickelten Modells eine Untersuchung verschiedener Einschluss-Strömungswerte im Kamin durchgeführt, wobei die Stillstandstiefe für jeden Einschluss-Strömungswert graphisch dargestellt wird. Die Strömungsdarstellung zeigt, dass für eine Einschluss-Strömung größer als 0.16 m3/h kein radioaktives Wasser durch den Kamin vom Kern zum Reaktorbecken aufsteigt. Die Modellergebnisse werden analysiert und diskutiert.
References
1Kupferman, R.: A Central-Difference Scheme for a Pure Stream Function Formulation of Incompressible Viscous Flow. SIAM Journal of Scientific Computing-Society of Industrial and Applied Mathematics23 (2001) 1Search in Google Scholar
2Chudanov, V. V.; Popkov, A. G.; Churbanov, A. G.; Vabishchevich, P. N.; Makarov, M. M.: Operator-Splitting Schemes for the Stream Function-Vorticity Formulation. Computers & Fluids24 (1995) 771Search in Google Scholar
3Jian-GueLiu; Weinan, E.: Simple Finite Element Method in Vorticity Formulation for Incompressible Flows. Mathematics of Computation S 0025-5718(00)01239-4, 2000Search in Google Scholar
4Shames, I. H.: Mechanics of Fluid. McGraw-Hill, Inc., International Edition 1992Search in Google Scholar
5Klein, S. A.; Beckman, W. A.; Myest, G. E.: FEHT program: Finite Element Analysis. Version 7.004, 1996-7Search in Google Scholar
© 2006, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Minor actinide burning in a CANDU thorium reactor
- Modeling of the TOSQAN test facility with the lumped parameter code COCOSYS
- Thermal-hydraulic modeling of the onset of flow instability in MTR reactors
- 10.3139/124.100302
- 10.3139/124.100304
- Radiation transfer in inhomogeneous exponential media
- Neutron transport problems for extremely anisotropic scattering
- Milne problem for isotropic and linearly anisotropic scattering for specular and diffuse reflecting boundary conditions solved with the HN method
- ICDE-results on complete common cause failures in the light of results obtained with the POS model
- Modelling of the cumulative behaviour of Caesium and Strontium activities in nuclear fuel
- Analytical study of the closure flow inside the ETRR-2 core chimney
- Minimizing radiation exposure for the reactor staff during the dismantling of a TRIGA research reactor
