1956•Nuclear Science and EngineeringRequires access

A Method of Analysis of Natural Circulation Boiling Systems

P.A. Lottes, W.S. Flinn

Abstract

The analysis presented has been developed for use in designing natural circulation boiling water nuclear reactors. Preliminary experimental information is given on density of steam water mixtures, velocity ratios of steam to water, and two phase friction factors for boiling in a vertical channel with uniform heat input. Experimental results of a natural circulation 600 psi boiling facility are compared with analytical results using this method.

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Key concepts: Natural circulation, Boiling, Boiling water reactor, Nuclear engineering, Circulation (fluid dynamics), Mechanics, Thermodynamics, Nuclear reactor