In this article, we study mixing in a fuel rod bundle geometry used in VVER-440 type pressurized water reactors. The flow inside the fuel assembly under normal operation is simulated using the FLUENT 6.3 computational fluid dynamics (CFD) solver. Steady state one phase Reynolds-averaged Navier-Stokes modeling is applied with two-equation turbulence models. In the first part of the article, grid independence is studied using a small submodel of the fuel rod bundle. In the second part, flow across a full-length fuel rod bundle is simulated both with constant temperature and with prescribed heat fluxes at the rod walls. Finally, in the third part of the article, we study how guiding vanes included in the spacer grids would enhance mixing in the hottest subchannels. We propose that having four guiding vanes on each side of the hexagonal spacer grid would produce most mixing in the desired locations of the fuel rod bundle.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4355-0
PROCEEDINGS PAPER
CFD Study on Mixing in VVER-440 Fuel Rod Bundle With Guiding Vanes in Spacer Grids
Tellervo Brandt,
Tellervo Brandt
Fortum Nuclear Services Ltd., Espoo, Finland
Search for other works by this author on:
Timo Toppila
Timo Toppila
Fortum Nuclear Services Ltd., Espoo, Finland
Search for other works by this author on:
Tellervo Brandt
Fortum Nuclear Services Ltd., Espoo, Finland
Timo Toppila
Fortum Nuclear Services Ltd., Espoo, Finland
Paper No:
ICONE17-75316, pp. 355-363; 9 pages
Published Online:
February 25, 2010
Citation
Brandt, T, & Toppila, T. "CFD Study on Mixing in VVER-440 Fuel Rod Bundle With Guiding Vanes in Spacer Grids." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 355-363. ASME. https://doi.org/10.1115/ICONE17-75316
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS
ASME J of Nuclear Rad Sci (October,2022)
Benchmark Experiments for Steady-State Natural Convection in Fuel Rod Bundles
J. Verif. Valid. Uncert (June,2017)
Damkohler Number Analysis in Lean Blow-Out of Toroidal Jet Stirred Reactor
J. Eng. Gas Turbines Power (October,2018)
Related Chapters
Completing the Picture
Air Engines: The History, Science, and Reality of the Perfect Engine
Control and Operational Performance
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Concluding remarks
Mechanical Blood Trauma in Circulatory-Assist Devices