Analysis of the secondary flow effect on turbulent flow in nuclear fuel bundles
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:6024355
- Seoul National Univ. (Korea)
It is important in nuclear fuel bundles to predict the exact velocity profile of the fluid, which allows the accurate calculation of the fuel temperature field. It may be very difficult, however, to analyze the flow phenomena due to the complex turbulent mechanism in such a closely packed geometry, where the secondary flow is also active. The name secondary flow is used for a time-mean motion conceived to be superposed on or embedded in a basic or primary flow and enhances the heat transfer in a subchannel. In this study, the secondary flow in infinite triangular arrays of parallel rods has been analyzed by a single-equation turbulent model for various Reynolds numbers and the pitch-to-diameter (P/D) ratio. The governing equations were for the two-dimensional, steady-state, and axially fully developed turbulent flow of an incompressible fluid with constant properties. Conclusively, the more precise turbulence model, including the secondary flow and anisotropic eddy viscosity, can be recommended to be used to obtain the accurate velocity profile and thus the temperature field, which is important in nuclear reactor safety analysis.
- OSTI ID:
- 6024355
- Report Number(s):
- CONF-900608--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 61
- Country of Publication:
- United States
- Language:
- English
Similar Records
Turbulence modeling of axial flow in a bare rod bundle
Experimental and analytical study of axial turbulent flows in an interior subchannel of a bare rod bundle
Predicted secondary flows in triangular array rod bundles
Journal Article
·
Wed Oct 31 23:00:00 EST 1979
· J. Heat Transfer; (United States)
·
OSTI ID:5664326
Experimental and analytical study of axial turbulent flows in an interior subchannel of a bare rod bundle
Conference
·
Sat May 01 00:00:00 EDT 1976
· J. Heat Transfer; (United States)
·
OSTI ID:7348296
Predicted secondary flows in triangular array rod bundles
Conference
·
Sat Sep 01 00:00:00 EDT 1979
· J. Fluids Eng.; (United States)
·
OSTI ID:5664418
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCURACY
ANISOTROPY
CURRENTS
EDDY CURRENTS
ELECTRIC CURRENTS
ENERGY TRANSFER
FLUID MECHANICS
FUEL CHANNELS
HEAT TRANSFER
HYDRAULICS
MECHANICS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR LATTICES
REYNOLDS NUMBER
STEADY-STATE CONDITIONS
TURBULENCE
TWO-DIMENSIONAL CALCULATIONS
VELOCITY
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCURACY
ANISOTROPY
CURRENTS
EDDY CURRENTS
ELECTRIC CURRENTS
ENERGY TRANSFER
FLUID MECHANICS
FUEL CHANNELS
HEAT TRANSFER
HYDRAULICS
MECHANICS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR LATTICES
REYNOLDS NUMBER
STEADY-STATE CONDITIONS
TURBULENCE
TWO-DIMENSIONAL CALCULATIONS
VELOCITY