Given that the average number of fast neutrons emitted following the thermal-neutron induced fission of 235U...

Given that the average number of fast neutrons emitted following the thermal-neutron induced fission of 235U is 2.42 per fission event; use the following data to calculate the mean number of fission neutrons produced per initial thermal neutron in a large volume sample of
(a) pure 235U (b) natural uranium 238U, and (c) uranium enriched to 3% in the 235U isotope.
Note: The microscopic absorption cross section for 235U is 694 barns. The cross section for 238U is 2.71 barns. The fission cross section for 235U is 582 barns. Natural uranium contains 0.7% 235U.
Comment on you results in terms of operation of a thermal reactor of finite size.

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genius_generous answered 1 year ago

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