Published December 2012 | Version v1
Journal article

Evaluation of frictional pressure drop correlations for two-phase flow in pipes

  • 1. Institute of Air Conditioning and Refrigeration, Nanjing University of Aeronautics and Astronautics, 29 Yudao St., Nanjing 210016 (China)

Description

Highlights: ► We investigate extensive correlations and experimental data sets for evaluation. ► We verify the correlations under various classifications of conditions. ► Two correlations which can give the best predictions are found. ► Factors that affect the predictions are analyzed systematically. - Abstract: The calculation of frictional pressure drop for two-phase flow in pipes is required by a variety of design practices. In the past six decades, many correlations for two-phase frictional pressure drop were proposed, and some evaluations were provided. However, both the correlations and the experimental data included in the existing evaluation literature are limited, which makes the evaluation results inconsistent and inaccurate. This work conducts a comprehensive survey of correlations and experimental investigations of two-phase frictional pressure drop. There are 29 correlations reviewed, and 3480 experimental data points are obtained from the open literature, with the experimental range of hydraulic diameters from 0.0695 to 14 mm, and mass flux from 8 to 6000 kg/m2 s. The reviewed correlations are evaluated against the experimental data, and two correlations which can present the most agreeable predictions are found.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2012.08.007

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2012.08.007;
PII
S0029-5493(12)00438-4;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
253
Journal Page Range
p. 86-97
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
44025360
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Numerical Data
Descriptors DEI
DESIGN; EVALUATION; EXPERIMENTAL DATA; HYDRAULICS; PIPES; PRESSURE DEPENDENCE; PRESSURE DROP; TWO-PHASE FLOW
Descriptors DEC
DATA; FLUID FLOW; FLUID MECHANICS; INFORMATION; MECHANICS; NUMERICAL DATA; TUBES

Optional Information

Copyright
Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.