| Nuclide | MAT | Numerical Data | Comments | Figures*) | Sig. table |
| 92-U -230 | 9213 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 92-U -231 | 9216 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 92-U -232 | 9219 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 92-U -233 | 9222 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 1] (2012/09/14) | original , 0K , 300K | comment | ↑ | ↑ | |
| 92-U -234 | 9225 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 2] (2013/07/10) | original , 0K , 300K | comment | ↑ | ↑ | |
| 92-U -235 | 9228 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 1] (2012/09/14) | original , 0K , 300K | comment | ↑ | ↑ | |
| 92-U -236 | 9231 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 92-U -237 | 9234 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| 92-U -238 | 9237 | original , 0K , 300K | comment | Fig1 Fig2 Fig3 Fig4 | table |
| [update 1] (2012/09/14) | original , 0K , 300K | comment | ↑ | ↑ | |
|
*) 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. |
|||||
