Application of the PHOENICS Code to LMFBR Plenum Analysis

  • P. J. Phelps
  • D. Kirkcaldy
  • B. Purslow
Conference paper
Part of the Lecture Notes in Engineering book series (LNENG, volume 18)

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.

Keywords

Porosity Convection Enthalpy Lime 

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

References

  1. [1]
    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.CrossRefGoogle Scholar
  2. [2]
    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.Google Scholar

Copyright information

© Springer-Verlag Berlin, Heidelberg 1986

Authors and Affiliations

  • P. J. Phelps
    • 1
  • D. Kirkcaldy
    • 1
  • B. Purslow
    • 2
  1. 1.CHAM LimitedWimbledonUK
  2. 2.National Nuclear CorporationRisley, CheshireUK

Personalised recommendations