Calculate the macroscopic thermal neutron absorption cross section for natural uranium. (ignore the trace amounts of 234U; the a/o of 235U in natural uranium is .72, and the a/o of the 238U is .9928).
Calculate the macroscopic thermal neutron absorption cross section for uranium enriched to 5% a/o 235U.
Calculate the mean free path for scattering of neutrons in light water. The scattering cross-section for water is 103 barns and the number density of water is .03343x1024atoms/cm3.
Plot on an Excel graph the change in the absorption cross section of 10B over the temperature range of 68°F to 600°F. Assume the microscopic absorption cross-section of 10B is 3840 barns at 68°F.