Table A-3.
Cross sections of isotopes undergoing fissions.
| Isotope | Reaction | Cross section (barn) |
|---|---|---|
| 235U | Fission | 26.239 |
| ν fission | 63.987 | |
| total | 42.677 | |
| Elastic | 8.773 | |
| Inelastic | 0.794 | |
| Absorption | 33.107 | |
| 238U | Fission | 0.08565 |
| ν fission | 0.239 | |
| total | 11.623 | |
| Elastic | 9.624 | |
| Inelastic | 1.007 | |
| Absorption | 0.990 | |
| 239Pu | Fission | 71.34 |
| ν fission | 204.0 | |
| total | 122.7 | |
| Elastic | 9.046 | |
| Inelastic | 5.886 | |
| Absorption | 113,08 | |
| Total flux n/(cm2 *s) | 101,06 ** |
** Note The fluence calculation process described in Appendix B leads to a fluence value equal to 8.46 1021 n/cm2 or to a total neutron flux at 1.79 109 n/(cm2.s) constant throughout the duration of the phenomenon (These values are associated with the effective sections given in Tab. A-3).
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