Published 2009 | Version v1
Miscellaneous

Characteristics of drift-flux models for the 3' diameter vertical-upward air-water flow condition

  • 1. KAERI, Daejeon (Korea, Republic of)

Description

One of the more complex aspects of two-phase flow calculations is the determination of the void fraction. An accurate estimation of this parameter is important for understanding and predicting the behavior of systems during a wide variety of transient conditions. The drift-flux models are based on correlations to compute the void fraction distribution and slip in a two-phase flow needed to obtain the relative velocity between the phases. Thus, the accuracy of the correlation has a decisive role in determining the correct transport of the two-phases in the system. In this paper, the assessment of 7 correlations based on the Zuber-Findlay model has been done by using the experimental data which were performed on the 3' diameter vertical-upward air-water test facility in KAERI. The void fraction was measured by using the impedance void meter which has a good dynamic resolution to get the values directly without any further data treatment. A total of 28 flow conditions have been performed at 2 bar and 3 bar inlet pressure conditions with temperature of 30 .deg. C, superficial liquid and gas velocity range of 0.5-2.8 m/s and 0.044-1.025 m/s. Some physical phenomena relevant to inlet flow condition and pressure effect were investigated. The results of assessment show a good predictive capability of Bestion model, which is currently used in the system code CATHARE

Part of:
Proceedings for the Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4)

Additional details

Publishing Information

Publisher
KAERI
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings for the Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4)
Imprint Pagination
534 p.
Journal Page Range
p. 202-210

Conference

Title
4. Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics
Dates
18-20 May 2009
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
40081996
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
C CODES; CORRELATIONS; EXPERIMENTAL DATA; PRESSURE DEPENDENCE; TRANSIENTS; TWO-PHASE FLOW; VOID FRACTION
Descriptors DEC
COMPUTER CODES; DATA; FLUID FLOW; INFORMATION; NUMERICAL DATA

Optional Information

Notes
10 refs, 9 figs, 2 tabs