Generalized drift flux correlation for vertical flow

Journal Article · Thu Oct 01 04:00:00 EDT 1992 · Nuclear Science and Engineering; (United States)

OSTI ID:7024036

Takeuchi, K; Young, M Y; Hochreiter, L E ^[1]

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1. Westinghouse Electric Corp., Pittsburgh, PA (United States). Nuclear and Advanced Technology Div.

Wallis' flooding correlation is generalized for both small and large pipes by the use of the critical Kutateladze number. A drift flux correlation is then obtained that is tangential to the generalized flooding curve. A simple function of void fraction for the correlation parameter is sufficient to provide good agreement with steam generator test data, without using flow regime maps. After the drift flux correlation is determined with the large-pipe test, it is implemented in the TRAC-PD2 computer code to be tested against the flooding curve for a small-diameter pipe. The Chexal-Lellouche formulas are also applied to the data analysis, and the results are compared with the present correlations. In this paper, discussion is extended to the Zuber-Findlay method of data analyses for the drift velocity and the distribution parameter, in relation to the flooding curve.

• OSTI ID: 7024036
• Journal Information: Nuclear Science and Engineering; (United States), Journal Name: Nuclear Science and Engineering; (United States) Vol. 112:2; ISSN NSENAO; ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BOILERS
COMPUTER CODES
CORRELATION FUNCTIONS
DATA
DATA ANALYSIS
DIFFUSION
DIMENSIONS
DISTRIBUTION
FLUID FLOW
FUNCTIONS
INFORMATION
PIPES
STEAM GENERATORS
T CODES
TESTING
VAPOR GENERATORS
VOID FRACTION