Void fraction prediction in two-phase flow across a tube bundle
Journal Article
·
· AIChE Journal (American Institute of Chemical Engineers); (United States)
- Dept. of Chemical Engineering and Applied Chemistry, Univ. of Toronto, Toronto, Ontario, M5S 1A4 (CA)
The hydrodynamics of two-phase flow has been investigated extensively for in-tube flows and for parallel flows in tube bundles. Very limited work has been performed, however, on vertical two-phase flows across tube bundles, which occur frequently on the shell side of heat exchangers such as kettle reboilers used in the process and other industries. In recent years, a few articles have been published on the measurement and prediction of void fraction in adiabatic, vertical air-water flow across horizontal rod bundles.
- OSTI ID:
- 5257355
- Journal Information:
- AIChE Journal (American Institute of Chemical Engineers); (United States), Journal Name: AIChE Journal (American Institute of Chemical Engineers); (United States) Vol. 38:4; ISSN AICEA; ISSN 0001-1541
- 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
FLOW RATE
FLUID FLOW
FLUID MECHANICS
HYDRODYNAMICS
MECHANICS
PERFORMANCE TESTING
PRESSURE DROP
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
ROD BUNDLES
TESTING
TWO-PHASE FLOW
VOID FRACTION
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420400* -- Engineering-- Heat Transfer & Fluid Flow
FLOW RATE
FLUID FLOW
FLUID MECHANICS
HYDRODYNAMICS
MECHANICS
PERFORMANCE TESTING
PRESSURE DROP
REACTOR COMPONENTS
REACTOR SAFETY EXPERIMENTS
ROD BUNDLES
TESTING
TWO-PHASE FLOW
VOID FRACTION