CDFR — Diagrid Hydraulic Analysis Using the Phoenics Code

  • G. A. Brown
  • P. J. Phelps
Part of the Lecture Notes in Engineering book series (LNENG, volume 18)


The PHOENICS code has been used to simulate the complex flow patterns in the diagrid region of a proposed CDFR design of fast reactor. The computer model is being used to complement experimental investigations using a reduced-scale water model, from which the first data are expected shortly.

The initial PHOENICS predictions appear credible, and some preliminary parameter studies of model inputs have been performed to establish the sensitivity of the predictions, whilst validation data is awaited.


Annular Flow Duct Wall Liquid Sodium Axial Velocity Component Outer Annulus 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.


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    ZUKAUSKAS A (1972) ‘Heat Transfer from Tubes in Crossflow’. Advances in Heat Transfer. Vol 8. pp 93–158. Academic Press, New York.Google Scholar
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    HINZE J O (1975) ‘Turbulence’. 2nd Edition, McGraw-Hill. New York.Google Scholar
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    ADAMSON J & LILLINGTON J N (1980) ‘Problems of Turbulence Modelling in Subchannel Geometries’. Paper presented at IAHR Workshop Group on Refined Modelling of Flows, Karlsruhe, October 1980.Google Scholar

Copyright information

© Springer-Verlag Berlin, Heidelberg 1986

Authors and Affiliations

  • G. A. Brown
    • 1
  • P. J. Phelps
    • 2
  1. 1.United Kingdom Atomic Energy AuthorityRisley, CheshireUK
  2. 2.Concentration Heat & Momentum LimitedWimbledon, LondonUK

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