ATHOS3 computer code verification: Volume 2, 0. 95-scale test: Final report
Technical Report
·
OSTI ID:5012899
As Part II of the EPRI Research Project S-310-8 for ATHOS3 code verification applications, the December 1985 version of the ATHOS3 code was used to analyze the flow field in the 0.95 scale test model of the Westinghouse Model D4 steam generator preheater. The test model is a 90/degree/ segment of the preheater region consisting of the entire five flow passes in the preheater. The experiments were conducted using ambient air as the working fluid. Tube surface velocities at tube Row 49, Passes 1, 2 and 3, tube Row 47, Pass 1 and at the back of the T-slot of the tube bundle were measured and compared with ATHOS3 predictions. ATHOS3 analysis models in both cylindrical and Cartesian coordinate systems were prepared. Coefficients in the correlations for friction factor and turbulence effective viscosity were varied in the calculations. Pressure differentials between various locations inside the test model were also measured and compared with code predictions. The results of the code verification with the test data are presented in this report.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA)
- OSTI ID:
- 5012899
- Report Number(s):
- EPRI-NP-5557-Vol.2; ON: TI88011937
- Country of Publication:
- United States
- Language:
- English
Similar Records
ATHOS3 computer code verification: Volume 1, 2/3-scale test: Final report
Verification of the ATHOS3 code against feedring and preheat steam generator test data: Final report
Comparison of Athos predictions of tube bundle cross-flow velocity with experimental data
Technical Report
·
Wed Jun 01 00:00:00 EDT 1988
·
OSTI ID:5012005
Verification of the ATHOS3 code against feedring and preheat steam generator test data: Final report
Technical Report
·
Sun May 01 00:00:00 EDT 1988
·
OSTI ID:7037761
Comparison of Athos predictions of tube bundle cross-flow velocity with experimental data
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:5688608
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
A CODES
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
DOCUMENT TYPES
FLUID FLOW
FLUID MECHANICS
HEAT EXCHANGERS
HYDRAULICS
MECHANICAL VIBRATIONS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROGRESS REPORT
PWR TYPE REACTORS
REACTORS
ROD BUNDLES
SIMULATION
STEAM GENERATORS
TESTING
THERMAL POWER PLANTS
TUBES
VALIDATION
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
A CODES
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
DOCUMENT TYPES
FLUID FLOW
FLUID MECHANICS
HEAT EXCHANGERS
HYDRAULICS
MECHANICAL VIBRATIONS
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROGRESS REPORT
PWR TYPE REACTORS
REACTORS
ROD BUNDLES
SIMULATION
STEAM GENERATORS
TESTING
THERMAL POWER PLANTS
TUBES
VALIDATION
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR