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Conference Article: Heat removal by natural circulation in gas-cooled rod-bundles

Abstract

Experimental and analytical investigations in the field of gas-cooled reactor core thermal hydraulics were performed at EIR since 1964. Temperature and pressure distributions in rod bundles of different geometries and rod surfaces were measured over a wide range of low conditions, stating at high turbulent Reynolds numbers, over transition region and to the laminar flow regime. The aim of these rod bundle heat transfer and fluid flow experiments was o prove the quality of the results calculated by comprehensive subchannel analysis therma-hydraulic computer codes (code verification) under nominal as well as transient reactor conditions. The measurements were used to assess the reliability of the analytical models and the accuracy of their predictions for design purposes.

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Reference:

Specialists' meeting on heat exchanging components of gas-cooled reactors Duesseldorf (Germany) 16-19 Apr 1984

International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria)

IWGGCR--9, pp:551-561