Abstract
Differential thermal expansion and swelling of fuel pins, hexagonal flow ducts and fuel spin spacers, fuel pin bowing between the spacers due to subchannel temperature differentials, and fuel pin bundle bowing due to the cambered hexagonal wrapper tube were analyzed for sodium-cooled fast reactor fuel assemblies. A FORTRAN IV computer program (CDA) was developed to calculate the flow area of the deformed coolant channels. This is subsequently fed into a conventional thermal analysis code, such as COBRA-II, to obtain the converged temperature distribution with the fuel assembly of interest.
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