Abstract
The paper describes the experimental and theoretical predictions of the flow behaviour in the inlet and outlet regions of the CDFR steam generator (SGU).
The CDFR-SGU shown on Fig 1 is of the ‘J’ tube style with high resistance grids providing the tube supports. Flow enters and leaves by annuli and has to turn twice through 180 degrees and flow across and parallel to the tubes.
The vertical variation of velocity through the outer-most row of tubes is important from vibration considerations. The flow distribution in the cross flow region influences the resultant parallel flow distribution and the heat transfer between the fluids. The accurate prediction of flow distributions in the two cross-flow regions (at inlet and outlet) is therefore required.
Progress towards achieving an understanding of cross-flow phenomena and the roles of the experiment and PHOENICS code predictions are described.
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References
Brown G A, “Thermal Hydraulic Analysis for the CDFR Steam Generator Unit (A Once-through Boiler) Using the BESANT Computer Code”. To be presented at the 3rd International Conference on Boiler Dynamics and Control in Nuclear Power Stations. 21–25 October 1985, Harrogate, England.
Zukauskas A, “Heat Transfer from Tubes in Cross-flow”. Advances in Heat Transfer, Vol 8, 1972, pp 93–158, Academic Press, New York, 1972.
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© 1986 Springer-Verlag Berlin, Heidelberg
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Brown, G.A., Scriven, J., UKAEA Risley. (1986). Shell-Side Hydraulic Phenomena in the Inlet and Outlet Regions of the CDFR Steam Generators. In: Markatos, N.C., Cross, M., Tatchell, D.G., Rhodes, N. (eds) Numerical Simulation of Fluid Flow and Heat/Mass Transfer Processes. Lecture Notes in Engineering, vol 18. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-82781-5_17
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DOI: https://doi.org/10.1007/978-3-642-82781-5_17
Publisher Name: Springer, Berlin, Heidelberg
Print ISBN: 978-3-540-16377-0
Online ISBN: 978-3-642-82781-5
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