10B.4 Heat conduction in a nuclear fuel rod assembly. Consider a long cylindrical nuclear fuel rod,...

 

Transcribed Image Text:

10B.4 Heat conduction in a nuclear fuel rod assembly. Consider a long cylindrical nuclear fuel rod, surrounded by an annular layer of aluminum cladding (see Fig. 10B.4). Within the fuel rod heat is produced by fission; the rate energy production per unit volume depends on position approximately as (10B.4-1) 1+b RE = Sno Here So 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 T. The heat-transfer coefficient at the cladding-coolant interface ish, and the thermal conductivities of the fuel rod and cladding are kç and kc. b kc Re 1+ + In Answer: TEmax – T = 4k- 2kc Rch Rp Fig. 10B.4 Temperature distribution in a cylindrical fuel-rod assembly. Coolant Aluminum cladding Nuclear fuel rod TF Tc -RF Rc TL 10B.4 Heat conduction in a nuclear fuel rod assembly. Consider a long cylindrical nuclear fuel rod, surrounded by an annular layer of aluminum cladding (see Fig. 10B.4). Within the fuel rod heat is produced by fission; the rate energy production per unit volume depends on position approximately as (10B.4-1) 1+b RE = Sno Here So 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 T. The heat-transfer coefficient at the cladding-coolant interface ish, and the thermal conductivities of the fuel rod and cladding are kç and kc. b kc Re 1+ + In Answer: TEmax – T = 4k- 2kc Rch Rp Fig. 10B.4 Temperature distribution in a cylindrical fuel-rod assembly. Coolant Aluminum cladding Nuclear fuel rod TF Tc -RF Rc TL