Benchmarking Computational Fluid Dynamics for Application to PWR Fuel
Conference
·
OSTI ID:21072813
- Westinghouse Nuclear Fuel (United States)
- Westinghouse Electric Corporation, Science and Technology Center, 1310 Beulah Road, Pittsburgh, PA 15235-5098 (United States)
- Thermal-Fluid Sciences Research Laboratory, Department of Mechanical Engineering, Clemson University, Clemson, SC 29634 (United States)
The present study demonstrates a process used to develop confidence in Computational Fluid Dynamics (CFD) as a tool to investigate flow and temperature distributions in a PWR fuel bundle. The velocity and temperature fields produced by a mixing spacer grid of a PWR fuel assembly are quite complex. Before using CFD to evaluate these flow fields, a rigorous benchmarking effort should be performed to ensure that reasonable results are obtained. Westinghouse has developed a method to quantitatively benchmark CFD tools against data at conditions representative of the PWR. Several measurements in a 5 x 5 rod bundle were performed. Lateral flow-field testing employed visualization techniques and Particle Image Velocimetry (PIV). Heat transfer testing involved measurements of the single-phase heat transfer coefficient downstream of the spacer grid. These test results were used to compare with CFD predictions. Among the parameters optimized in the CFD models based on this comparison with data include computational mesh, turbulence model, and boundary conditions. As an outcome of this effort, a methodology was developed for CFD modeling that provides confidence in the numerical results. (authors)
- Research Organization:
- The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 21072813
- Country of Publication:
- United States
- Language:
- English
Similar Records
Toward High Fidelity LES Simulations of 5 x 5 PWR Fuel Bundle with Mixing Vane
High Resolution Stereoscopic PIV Measurements in a 5 x 5 Rod Bundle with Mixing Vane
Large Eddy Simulation of turbulent flow in rod bundle with spacer grids
Journal Article
·
Sat Jul 01 00:00:00 EDT 2017
· Transactions of the American Nuclear Society
·
OSTI ID:23050420
High Resolution Stereoscopic PIV Measurements in a 5 x 5 Rod Bundle with Mixing Vane
Journal Article
·
Sat Jul 01 00:00:00 EDT 2017
· Transactions of the American Nuclear Society
·
OSTI ID:23050384
Large Eddy Simulation of turbulent flow in rod bundle with spacer grids
Journal Article
·
Sat Jul 01 00:00:00 EDT 2017
· Transactions of the American Nuclear Society
·
OSTI ID:23050419