Comparison of Athos predictions of tube bundle cross-flow velocity with experimental data

Conference · Thu Jan 01 04:00:00 EST 1987

OSTI ID:5688608

Lee, A Y; Masiello, P J; Steininger, D A

The cross-flow velocity components along the tube gaps spanning the height between two support plates at several front rows of tubes, in the T-slot (untubed area) and at the annulus between the wrapper boundary and the tube bundle periphery, were measured in a 2/3 scale test model of the first flow pass of the Westinghouse Model D4 steam generator preheater. The measured single-phase water velocities were compared with the predictions obtained from the ATHOS code (in no heat transfer option). The code predicted the secondary flows generated in the vertical feedwater flow passage and the flow reversal at the inner corner of the 90/sup 0/ bend at the entrance to the bundle. The predicted axial profiles of inward tube-gap velocity component for the front row of tubes are quite smooth, missing the local variations of curvatures as observed in the test data. Agreement is generally good for the tube gaps in the interior of the bundle.

• OSTI ID: 5688608
• Report Number(s): CONF-861211-
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
A CODES
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSSFLOW SYSTEMS
FLOW MODELS
FLOW RATE
FLUID FLOW
FLUID MECHANICS
HEAT EXCHANGERS
HEATERS
HYDRAULICS
HYDROGEN COMPOUNDS
INCIDENCE ANGLE
LIQUID FLOW
MATHEMATICAL MODELS
MECHANICS
OXYGEN COMPOUNDS
SCALE MODELS
SIMULATION
STEAM GENERATORS
STRUCTURAL MODELS
TUBES
VAPOR GENERATORS
WATER