The neutron flux in a hypothetical reactor is approximately 4 x 10^15 neutrons/cm2s. The microscopic cross section

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Question:

The neutron flux in a hypothetical reactor is approximately 4 x 10^15 neutrons/cm2s. The microscopic cross section for fission is 250 barns. The density of U-235 target nuclei is 125 x 10^24 nuclei/cm3. Calculate the rate at which fission reactions are taking place. Give appropriate units.