A reactor core element is simulated by a coaxial sodium flow over a solid fuel rod. In terms of the following data, u” = 35 MW/m3, Di = 25 mm, D0 = 37.5 mm, ℓ = 6 m, Ti= 90 °C, V = 1.2 m/s, and kfuel rod = 9 W/m∙K, evaluate (a) the exit temperature of sodium, (b) the surface temperature of the fuel rod, and (c) the centerline temperature of the fuel rod.

 

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