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ISSN Online: 2377-424X

ISBN Print: 0-89116-130-9

International Heat Transfer Conference 6
August, 7-11, 1978, Toronto, Canada

TRANSIENT THERMOHYDRAULICS ANALYSIS FOR NUCLEAR REACTORS

Get access (open in a dialog) DOI: 10.1615/IHTC6.2520
pages 311-337

Abstract

In this paper we focus on transient boiling flow which is an important aspect in the design of water cooled nuclear reactors. A unique feature of the design methodology is the analysis of a spectrum of postulated accidents in which transient heat transfer and fluid flow considerations play a key role. A strategy for analysis development is outlined and the state-of-the-art of flow-boiling analysis is reviewed. We show that mathematical models which consider gas-liquid flows with unequal phase velocities and temperatures are needed. A theoretical framework is presented for one-dimensional duct flow and governing equations, of the hyperbolic type, appropriate for separated gas-liquid flow are derived. Other models, in common use, are then derived from the separated flow model by making simplifying assumptions about interphase and intraphase variations of the flow variables. Next, various numerical solution procedures are described and their performance is highlighted for specific problems. Finally, existing experiments are reviewed with respect to model development needs and requirements for new experiments are outlined.