Study of the stratified-slug flow transition in a horizontal pipe containing a rod bundle
The experimental measurements related to the stratified-slug flow transition in a horizontal pipe containing a 7-rod bundle are described. The experiments were carried out in air-water and Freon gas-water flows with liquid-to-gas density ratios in the range 46 to 392. The results are compared with the predictions of a modified form of the Taitel-Dukler theory. The predictions are also compared with other published experimental data on the stratified-slug flow transition in air-water and steam-water flows in pipes containing 37-rod bundles. Reasonable agreement is obtained in all cases. This work has particular application to the study of heat transfer in the horizontal fuel channels of a CANDU nuclear reactor under certain postulated fault conditions.
- Research Organization:
- Atomic Energy of Canada Ltd., Pinawa, Manitoba
- OSTI ID:
- 5920034
- Journal Information:
- Annual Symposium on Simulation of Reactor Dynamics and Plant Control; (), Vol. 10
- Country of Publication:
- United States
- Language:
- English
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CANDU TYPE REACTORS
FUEL ELEMENT CLUSTERS
ROD BUNDLES
FLUID FLOW
HEAT TRANSFER
AIR
PIPES
STEAM
WATER
ENERGY TRANSFER
FLUIDS
FUEL ASSEMBLIES
GASES
HEAVY WATER MODERATED REACTORS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
PRESSURE TUBE REACTORS
REACTORS
THERMAL REACTORS
210400* - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated