Article ID Journal Published Year Pages File Type
5478020 Progress in Nuclear Energy 2017 12 Pages PDF
Abstract
Fuel assemblies of sodium cooled fast reactors are usually designed in wire wrapped configuration and subchannel analysis is an efficient approach for thermal hydraulic analysis of wire wrapped assemblies especially when two phase or transient analysis is required. As the subchannel method is a lumped parameter approach, for calculation of pressure drop and flow mixing, suitable correlations should be provided. So for subchannel analysis of wire wrapped assemblies various pressure drop and flow mixing correlations have been developed and reported in literatures. In this work, normalized temperatures of single phase sodium at the outlet of different channels of ORNL 19 pins wire wrapped bundle are calculated by subchannel approach. In these subchannel calculations, different pressure drop and flow mixing correlations are used. Then the calculated normalized temperatures are compared with experimental results of ORNL 19 pins bundle to find out which pressure drop and flow mixing correlations of wire wrapped assemblies, give the most accurate result.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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