A nuclear reactor fuel rod is a circular cylinder 6 cm in diameter. The rod is to be tested by cooling it with a flow of sodium at 205?C and a velocity of 5 cm/s Perpendicular to its axis. If the rod surface is not to exceed 300?C, estimate the maximum allowable power dissipation in the rod.GIVENCylinder in a cross flow of liquid sodiumCylinder diameter (D) = 6 cm = 0.06 mSodium temperature (T??) = 205?CSodium velocity (U??) = 5 cm/s = 0.05 m/sMaximum rod surface temperature (Ts) = 300?CASSUMPTIONSSteady stateTurbulence in the sodium flow approaching the rod is lowHeat generation per unit volume in the rod isuniform

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T-300°C Max D-6 cm Sodlum T.-205°C U--5 cm/s