Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
8067686 | Annals of Nuclear Energy | 2016 | 12 Pages |
Abstract
This paper assesses a popular tube-based mechanistic critical heat flux model (Hewitt and Govan's annular flow model (based on the model of Whalley et al.), and modifies and implements the model for bundle geometries. It describes the results of the ASSERT subchannel code predictions using the modified model, as applied to a single tube and the 28-element, 37-element and 43-element (CANFLEX) CANDU bundles. A quantitative comparison between the model predictions and experimental data indicates good agreement for a wide range of flow conditions. The comparison has resulted in an overall average error of â0.15% and an overall root-mean-square error of 5.46% with tube data representing annular film dryout type critical heat flux, and in an overall average error of â0.9% and an overall RMS error of 9.9% with Stern Laboratories' CANDU-bundle data.
Keywords
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Physical Sciences and Engineering
Energy
Energy Engineering and Power Technology
Authors
Najmeddine Hammouda, Zhong Cheng, Yanfei F. Rao,