Abstract
This paper reviews the role of the PHOENICS code in the assessment of various design configurations for the hot and cold pools in the primary circuit of the proposed CDFR nuclear reactor.
These pools are large volumes of liquid metal, and feature complex three-dimensional flow patterns and complicated flow geometries.
Two dimensional and latterly three-dimensional models have been used for some time to complement water-model experiments, and the paper reviews some of the recent work performed to validate the mathematical models.
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References
Markatos N C, Phelps P J and Purslow B (1982) ‘Computer Simulation of the Thermal-Hydraulic Behaviour of Fast Reactor Pools’. Annals of Nuclear Energy, Vol.9. 179–183. 1982.
Hawkins K S and Purslow B (1984) ‘Experimental and Theoretical Investigations into the Thermal Hydraulic Behaviour of a Fast Reactor Cold Poor’ Proc. 3rd International Conference on Liquid Metal Engineering and Technology in Energy Production. Oxford. April 1984.
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© 1986 Springer-Verlag Berlin, Heidelberg
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Phelps, P.J., Kirkcaldy, D., Purslow, B. (1986). Application of the PHOENICS Code to LMFBR Plenum Analysis. 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_13
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DOI: https://doi.org/10.1007/978-3-642-82781-5_13
Publisher Name: Springer, Berlin, Heidelberg
Print ISBN: 978-3-540-16377-0
Online ISBN: 978-3-642-82781-5
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