PROBLEM 2. U3Si2 fuel is used in nuclear research reactors. Uranium-235 enrichment is 20%. Density of U3Si2 is 12.2 g/cm. Assume Si has mass 28.09 g/mol, with microscopic absorption cross section of 0.177 barn. Again, assume that average energy released per fission reaction is 200 MeV. a) Calculate thermal neutron reproduction factor for this fuel. b) What is the thermal power density in this fuel at a point where the thermal neutrons flux is 31014 n/cm.s? c) Determine the power of the reactor if the mass of fuel is 150 kg and average flux is 1.01014 n/cm.s.