Consider a cylindrical nuclear fuel rod of length l and diameter d that is encased in a concentric tube. Pressurized water flows through the annular region between the rod and the tube at a rate , and the outer surface of the tube is well insulated. Heat generation occurs within the fuel rod, and the volumetric generation rate is known to vary sinusoidally with distance along the rod. That is(x)=0sin (x/l), where 0 (w/m3 ) is a constant. A uniform convection coefficient h may be assumed to exist between the surface of the rod and the water.
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