| Nuclide | MAT | Numerical Data | Comments | Figures*) | Sig. table |
| 95-Am-240 | 9540 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 95-Am-241 | 9543 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 1] (2013/07/10) | original , 0K , 300K | comment | ↑ | ↑ | |
| 95-Am-242 | 9546 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 95-Am-242m | 9547 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 95-Am-243 | 9549 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 1] (2012/09/14) | original , 0K , 300K | comment | ↑ | ↑ | |
| 95-Am-244 | 9552 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 95-Am-244m | 9553 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
|
*) Fig1, Fig2 and Fig3 are made from pointwise files at 300 K. Fig1 : Total, elastic and inelastic scattering, capture and fission cross sections Fig2 : Same as Fig1 but the cross sections are averaged in 70 energy group intervals Fig3 : Threshold reaction cross sections Fig4 : Number of prompt and delayed neutrons per fission ↑ : Same as the previous version above because cross sections were not changed. |
|||||
