ATHOS3 computer code verification: Volume 1, 2/3-scale test: Final report

Technical Report · Wed Jun 01 04:00:00 EDT 1988

OSTI ID:5012005

Lee, A Y; Masiello, P J

As part of an ATHOS3 code verification program as it relates to flow-induced tube vibration prediction, Westinghouse was contracted by the Steam Generator Project Office of EPRI in Project S-310-8, Part I to analyze the flow field in a Westinghouse 2/3 scale test model of the first pass of the preheat section of a Model D4 steam generator. The predicted velocities were to be compared with the test data obtained at midpoints between tube centers at tube Rows 49 (first row of tubes from feedwater entrance), 47, 45, and other locations. The tests were conducted with water at 60 psig and 100/degree/F. The tested water flow rate simulated the feedwater flow rate at full power conditions of a D4 steam generator. Analysis models in both cylindrical and Cartesian coordinates and different flow cell sizes were used in the code predictions. The measured total RMS forces on four front row tubes were also correlated with measured velocities at the four tubes. The results of the code verification with the test data are presented in this report.

• Research Organization: Westinghouse Electric Corp., Forest Hills, PA (USA). Steam Generator Technology Div.
• OSTI ID: 5012005
• Report Number(s): EPRI-NP-5557-Vol.1; ON: TI88011933
• 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
COMPUTER PROGRAM DOCUMENTATION
COMPUTERIZED SIMULATION
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
HEAT EXCHANGERS
HEAT TRANSFER
HYDRAULICS
MECHANICAL VIBRATIONS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
SIMULATION
STEAM GENERATORS
TESTING
THERMAL POWER PLANTS
VALIDATION
VAPOR GENERATORS