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.
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 |