Study of the stratified-slug flow transition in a horizontal pipe containing a rod bundle

Journal Article · Tue Jan 01 04:00:00 EST 1985 · Annual Symposium on Simulation of Reactor Dynamics and Plant Control; ()

OSTI ID:5920034

Krishnan, V S; Kowalski, J E

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; (), Journal Name: Annual Symposium on Simulation of Reactor Dynamics and Plant Control; () Vol. 10
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
AIR
CANDU TYPE REACTORS
ENERGY TRANSFER
FLUID FLOW
FLUIDS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
GASES
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
PIPES
PRESSURE TUBE REACTORS
REACTORS
ROD BUNDLES
STEAM
THERMAL REACTORS
WATER