Dynamic model for horizontal two-phase flow predicting low head flooding
Journal Article
·
· Numerical Heat Transfer. Part A, Applications; (United States)
- Technical Research Center of Finland, Espoo (Finland). Nuclear Engineering Lab.
The countercurrent flow of gas and water in a short horizontal pipe is studied numerically with a two-phase flow model. It is observed that the onset of flooding cannot be predicted at low liquid flow rates using conventional one-dimensional equations. The conventional equations yield the same underestimated results as the Taitel-Dukler criterion. Utilizing physical reasoning, improved equations have been derived. The basic idea is that the distribution of the phase velocities should not be treated as uniform in the cross-sectional area occupied by phases but transverse dependencies for the velocities should be allowed. By comparing measurement data and calculated results, it is shown that flooding transition can be predicted accurately with these equations.
- OSTI ID:
- 7192167
- Journal Information:
- Numerical Heat Transfer. Part A, Applications; (United States), Journal Name: Numerical Heat Transfer. Part A, Applications; (United States) Vol. 26:4; ISSN 1040-7782; ISSN NHAAES
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COOLANT LOOPS
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID FLOW
MATHEMATICAL MODELS
ORIENTATION
POWER REACTORS
PWR TYPE REACTORS
REACTORS
THERMAL REACTORS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COOLANT LOOPS
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FLUID FLOW
MATHEMATICAL MODELS
ORIENTATION
POWER REACTORS
PWR TYPE REACTORS
REACTORS
THERMAL REACTORS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS