Heat conduction in a nuclear fuel rod assembly (Fig. 10B.3) considers a long cylindrical nuclear fuel rod, surrounded by an annular layer of aluminum cladding. Within the fuel rod heat is produced by fission; this heat source depends on position approximately as
Here Sn0 and b are known constants, and r is the radial coordinate measured from the axis of the cylindrical fuel rod. Calculate the maximum temperature in the fuel rod if the outer surface of the cladding is in contact with a liquid coolant at temperature TL. The heat transfer coefficient at the cladding-coolant interface is hL, and the thermal conductivities of the fuel rod and cladding are ks andkC.
