Pin Bundles Hydraulic Characteristics of the BREST-OD-300 Wire-Spaced Fuel Subassemblies
Authors: Fomichev D.V., Solonin V.I. | Published: 15.04.2015 |
Published in issue: #2(101)/2015 | |
Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety | |
Keywords: experimental nuclear reactor, wire-spaced fuel subassembly, computational fluid dynamics |
Findings from numerical simulation of the flow in 37-rod fuel assembly model spaced by a double-wire tapered wrapping as applied to the BREST-OD-300 reactor plant, are presented. Data on a static pressure heightwise distribution within the dummies, and dependencies for determining the fuel bundle flow friction factors are obtained. Recommendations are provided on using the closing turbulence models available in the ANSYS Fluent CFD package. A comparative analysis is performed against the existing empirical dependencies for determining the flow friction factors. The calculated and experimental data compliance is demonstrated. Analysis of the experimental data as well as the numerical simulation results for hydrodynamic performance of the BREST-OD-300 fuel rod assembly are presented.
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