Question 5.2: Show that when a Uranium-235 nucleus absorbs a thermal neutr......

Show that when a Uranium-235 nucleus absorbs a thermal neutron, there is 85% chance that the nucleus will split apart, and that there is a 15% chance that the nucleus will simply capture the neutron and emit an energetic gamma ray in the process.

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From the cross sections shown in Table 5.6, we can see that the fission cross section for Uranium-235 is about 585 barns and that the radiative capture cross section is about 99 barns. The total absorption cross section for the thermal neutron is therefore σ_a = σ_c + σ_f = 585 barns + 99 barns = 684 barns.
The probability of the nucleus splitting apart due to fission alone is therefore P_f = σ_f/σ_a = 585/684 = 0.855, and the probability of the nucleus capturing the neutron and emitting a gamma ray is therefore P_c = σ_c/σ_a = 99/684 = 0.145. Note that if we had measured these probabilities as just as the ratio of the fission probability to the capture probability, then the values for these ratios would be P_c = σ_c/σ_f = 99/585 = 0.169 ≈ 17% and P_f = (1.0 – P_c) ≈ 83%, respectively. So the absorption of a neutron by a U-235 nucleus does not necessarily guarantee that it will split apart.

TABLE 5.6
Comparison of the Cross Sections for Several Common Nuclear Materials
Thermal Neutrons Fast Neutrons
E ≤ 1 eV E > 1 eV
Nuclear Material Fission Capture Scattering Fission Capture Scattering
Fuels (fissile) U-233 528.45 45.76 20.9 2.7323 0.27176 6.71
U-235 585.086 98.6864 14 1.9041 0.55549 6.73
Pu-239 747.401 270.329 7.7 1.7973 0.49614 6.98
Fuels (fertile) U-238 0.00001177 2.71692 8.871 0.042758 0.33188 6.87
Th-232 0 7.4 20.36 0.010193 0.38157 6.86
Cladding Zirconium 0 0.185396 6.46 0 0.0265766 5.82
Carbon steel 0 3.08668 11.62 0 0.0170228 5.18
Moderator or coolant Light water 0 0.664 103 0 0.00051554 16.9
Heavy water 0 0.00133 13.6 0 0.00011459 20.4
Liquid sodium 0 0.528 3.28 0 0.0027511 3.17
Graphite 0 0.0034 4.753 0 0.00031285 11.2
Control rods Boron-10 0 3840.0 5.24 0 2.73462 2.13
Cadmium 0 2424.15 6.5 0 0.266766 6.44
Other materials Hydrogen 0 0.332 30.33 0 0.0001 4.26
Helium 0 0.001 0.86 0 ~0 7.08
Oxygen 0 0.00027 3.87 0 ~0 8.22

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