Drift-flux Analysis in Horizontal Two-phase Flow

Journal Article · Fri Jul 01 00:00:00 EDT 2016 · Transactions of the American Nuclear Society

OSTI ID:23042887

Kong, Ran; Kim, Seungjin ^[1]; Bajorek, Stephen; Tien, Kirk; Hoxie, Chris ^[2]

---

1. Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, 230 Reber Building, University Park, PA 16802 (United States)
2. United States Nuclear Regulatory Commission, 11555 Rockville pike, Rockville, MD 20852 (United States)

While the most detailed approach to model two-phase flows is the two-fluid model, the drift-flux model may also provide effective methods for estimating one-dimensional two-phase flow parameters. For example, in the current nuclear system analysis codes, the interfacial drag force is a function of the void fraction, drift velocity, and area-averaged relative velocity, which are estimated based on drift-flux approach. While correlations for these parameters exist for vertical two-phase flows, correlations for horizontal two-phase flows have not been developed. (authors)

• OSTI ID: 23042887
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 115; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
71 CLASSICAL AND QUANTUM MECHANICS
GENERAL PHYSICS
DRAG
FLUIDS
FUNCTIONS
ONE-DIMENSIONAL CALCULATIONS
SYSTEMS ANALYSIS
TWO-PHASE FLOW
VOID FRACTION