Study of void fraction and mixing of immiscible liquids in a pool configuration by an upward gas flow
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:7232856
- Univ. of Wisconsin-Madison, Nuclear Engineering and Engineering Physics Dept., Madison, WI (US)
In this paper, investigations are performed to study the mixing between immiscible liquids in a pool configuration due to an upward gas flow. A water-R113 system is sued in the bubbly/churn-turbulent regimes to determine the effects of the unagitated pool depth on layer mixing. The superficial gas velocity at which full mixing is attained is observed to increase with the pool depth, although it is concluded that this is a weak dependency. Mixing in the churn-turbulent regime is studied with Wood's metal-water and Wood's metal-silicone fluid (100 cS) as pairs of fluids. Additional past mixing data from six other fluids are also included in the data base. A criterion is proposed to determine if two liquids will entrain in bubbly or churn-turbulent flow. Correlations are derived that, for a set of given conditions, allow prediction of the mixing state (mixed or segregated) of a system. Because of the indirect method of measuring the mixed layer thickness, pool void fraction experiments are also performed. For the case of water and R113, the effect of unagitated pool depth on the void fraction is studied.
- OSTI ID:
- 7232856
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 99:1; ISSN NUTYB; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BOILING
BUBBLES
BUILDING MATERIALS
CONCRETES
COOLING SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUIDS
FUEL-CLADDING INTERACTIONS
GAS FLOW
HEAT TRANSFER
MATERIALS
MELTING
PERFORMANCE TESTING
PHASE TRANSFORMATIONS
POOL BOILING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
SAFETY
TESTING
TURBULENT FLOW
VOID FRACTION
WORKING FLUIDS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
BOILING
BUBBLES
BUILDING MATERIALS
CONCRETES
COOLING SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUIDS
FUEL-CLADDING INTERACTIONS
GAS FLOW
HEAT TRANSFER
MATERIALS
MELTING
PERFORMANCE TESTING
PHASE TRANSFORMATIONS
POOL BOILING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY
SAFETY
TESTING
TURBULENT FLOW
VOID FRACTION
WORKING FLUIDS