Hydrodynamic behavior of a bare rod bundle. [LMFBR]
The temperature distribution within the rod bundle of a nuclear reactor is of major importance in nuclear reactor design. However temperature information presupposes knowledge of the hydrodynamic behavior of the coolant which is the most difficult part of the problem due to complexity of the turbulence phenomena. In the present work a 2-equation turbulence model--a strong candidate for analyzing actual three dimensional turbulent flows--has been used to predict fully developed flow of infinite bare rod bundle of various aspect ratios (P/D). The model has been modified to take into account anisotropic effects of eddy viscosity. Secondary flow calculations have been also performed although the model seems to be too rough to predict the secondary flow correctly. Heat transfer calculations have been performed to confirm the importance of anisotropic viscosity in temperature predictions. All numerical calculations for flow and heat have been performed by two computer codes based on the TEACH code. Experimental measurements of the distribution of axial velocity, turbulent axial velocity, turbulent kinetic energy and radial Reynolds stresses were performed in the developing and fully developed regions. A 2-channel Laser Doppler Anemometer working on the Reference mode with forward scattering was used to perform the measurements in a simulated interior subchannel of a triangular rod array with P/D = 1.124. Comparisons between the analytical results and the results of this experiment as well as other experimental data in rod bundle array available in literature are presented. The predictions are in good agreement with the results for the high Reynolds numbers.
- Research Organization:
- Massachusetts Inst. of Tech., Cambridge (USA). Dept. of Nuclear Engineering
- DOE Contract Number:
- EY-76-S-02-2245
- OSTI ID:
- 5154168
- Report Number(s):
- COO-2245-48TR
- Country of Publication:
- United States
- Language:
- English
Similar Records
Experimental and analytical study of axial turbulent flows in an interior subchannel of a bare rod bundle
Analysis of the secondary flow effect on turbulent flow in nuclear fuel bundles
Related Subjects
210500* -- Power Reactors
Breeding
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BREEDER REACTORS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
HEAT TRANSFER
HYDRODYNAMICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
MECHANICS
MOCKUP
REACTORS
SIMULATION
STRUCTURAL MODELS
TURBULENT FLOW