the cross section of a long cylindrical fuel element in a nuclear reac
The cross-section of a long cylindrical fuel element in a nuclear reactor is shown. Energy generation occurs uniformly in the thorium fuel rod which is of diameter D = 25 mm and is wrapped in a thin aluminum cladding. It is proposed that, under steady-state, conditions the system operates with a generation rate of 4-7x 108 W/m3 and cooling system characteristics of Too = 95°C and h= 7000 w/m2 K. Is this proposal satisfactory? (Hint: Think about material melting) * True * False
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