Application of the PHOENICS Code to LMFBR Plenum Analysis
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.
KeywordsPorosity Convection Enthalpy Lime
Unable to display preview. Download preview PDF.
- 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