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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  

DOI: 10.18698/0236-3941-2015-2-4-17

 
Category: Power, Metallurgic and Chemical Engineering | Chapter: Nuclear Reactor Engineering, Machines, Assemblies, and Nuclear Materials Technology  
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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