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