Problem 1. UA13 is used as a fuel in research nuclear reactor. Uranium-235 enrichment is 20%. Density of UAI3 is 6.8 g/cm. a) Calculate thermal neutron reproduction factor n for this fuel. b) What is the thermal power density in this fuel at a point where the thermal neutrons flux is 1.09x1013 n/cm²s? c) Determine power of the reactor if the mass of fuel is 75 kg and average flux is 1.0×101³ n/cm³s. Assume that average energy released per fission reaction is 200 MeV.

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