Three-dimensional Fast Flux Test Facility plenum model turbulent flow prediction and data comparison
Description
Two- and three-dimensional numerical simulations of turbulent flow in a scaled Fast Flux Test Facility (FFTF) upper plenum model were performed using the TEMPEST hydrothermal code. A standard k-element of model was used to describe turbulence through an effective viscosity. Comparisons with previously reported mean velocity and turbulence field data measured in the plenum model and two-dimensional numerical simulations using the TEACH code were made. Predicted horizontal and vertical mean velocities and turbulent kinetic energy are shown to be in good agreement with available experimental data when inlet conditions of the dissipation of turbulent kinetic energy are appropriately prescribed. The three-dimensional quarter-symmetry simulation predicts the turbulent kinetic energy field significantly better than the two-dimensional centerplane simulations. These results lead to conclusions concerning deficiencies in the experimental data and the turbulence model
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01 as DE82006170.
Files
Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- PNL-SA--9078
Conference
- Title
- 20. national heat transfer conference.
- Dates
- 2 - 5 Aug 1981.
- Place
- Milwaukee, WI (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14720609
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FFTF REACTOR; HYDRAULICS; HYDRODYNAMICS; MATHEMATICAL MODELS; REACTOR COMPONENTS; REACTOR CORES; THREE-DIMENSIONAL CALCULATIONS; TURBULENT FLOW; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- EPITHERMAL REACTORS; FAST REACTORS; FLUID FLOW; FLUID MECHANICS; LIQUID METAL COOLED REACTORS; MECHANICS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST REACTORS
Optional Information
- Secondary number(s)
- CONF-810804--25.