Solution-Thermal neutron absorption cross section for

Thermal neutron absorption cross section for natural uranium

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Reference no: EM131618955

1. 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).

2. Calculate the macroscopic thermal neutron absorption cross section for uranium enriched to 5% a/o 235U.

3. 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.

4. 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.

Reference no: EM131618955

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Thermal neutron absorption cross section for natural uranium

Reference no: EM131618955

Reference no: EM131618955

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