Large-eddy simulation - prediction of fluctuating lift and drag forces and comparison with experiment
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5875362
- Texas A M Univ., College Station (USA)
Excessive tube vibration caused by turbulent flow buffeting and fluid-elastic excitation is one of the main problems associated with steam generators. Vibration can lead to rupture of tubes within the steam generator, necessitating plugging, and perhaps even replacement of the component. Turbulence buffeting, and resulting excitation, is believed to be one of the mechanisms leading to tube vibration. The large-eddy simulation (LES) technique is being considered as a possible design analysis tool for defining the temporally fluctuating forces on steam generator tube banks. The present investigation uses LES to calculate the flow field for an array of tubes subject to turbulent flow and to compare the fluctuating lift and drag forces on a central tube with experimental findings. Predictions to date using LES methodology compare quite favorably with experimental data.
- OSTI ID:
- 5875362
- Report Number(s):
- CONF-901101--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 62
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
20 FOSSIL-FUELED POWER PLANTS
200101 -- Fossil-Fueled Power Plants-- Cooling & Heat Transfer Equipment & Systems
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCURACY
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
DIFFERENTIAL EQUATIONS
DRAG
EQUATIONS
FAILURES
FINITE DIFFERENCE METHOD
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FLUID-STRUCTURE INTERACTIONS
G CODES
ITERATIVE METHODS
MATHEMATICAL MODELS
MECHANICAL VIBRATIONS
MECHANICS
NAVIER-STOKES EQUATIONS
NUMERICAL SOLUTION
PARTIAL DIFFERENTIAL EQUATIONS
RUPTURES
SIMULATION
STEAM GENERATORS
THREE-DIMENSIONAL CALCULATIONS
TUBES
TURBULENT FLOW
VAPOR GENERATORS
VISCOSITY
200101 -- Fossil-Fueled Power Plants-- Cooling & Heat Transfer Equipment & Systems
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCURACY
BOILERS
COMPUTER CODES
COMPUTERIZED SIMULATION
DIFFERENTIAL EQUATIONS
DRAG
EQUATIONS
FAILURES
FINITE DIFFERENCE METHOD
FLOW MODELS
FLUID FLOW
FLUID MECHANICS
FLUID-STRUCTURE INTERACTIONS
G CODES
ITERATIVE METHODS
MATHEMATICAL MODELS
MECHANICAL VIBRATIONS
MECHANICS
NAVIER-STOKES EQUATIONS
NUMERICAL SOLUTION
PARTIAL DIFFERENTIAL EQUATIONS
RUPTURES
SIMULATION
STEAM GENERATORS
THREE-DIMENSIONAL CALCULATIONS
TUBES
TURBULENT FLOW
VAPOR GENERATORS
VISCOSITY