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Abstract
The results of experimental investigations of heat exchange and temperature fi elds in channels and fuel assemblies in lead-cooled fast reactors performed at the Leipunskii Institute for Physics and Power Engineering are presented. The main investigations were performed using mercury and lead-bismuth and sodium-potassium alloys. The effect of the contact thermal resistance on heat exchange is analyzed. Data on heat transfer and the azimuthal temperature nonuniformity of the fuel elements are compared for assemblies with a wide lattice, relative spacing s/d = 1.33, smooth fuel elements, and spacing of fuel elements by an ‘edge on edge’ double winding and transverse lattices are compared.
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