| CODE | NUCLIDE | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | NUCLIDE | COMMENTS |
| 1053131 | 53-I -131 | ENDF/B-VII | New MF=6 MT=102 taken from TENDL2011 (Replaces any existing Data) | / | / | / | / | / | / | / | / | CONVERTED FROM JENDL-3.3 BY NNDC OCT 2004 Corrected MF=3, MT=2 at 10.4881 MeV for SUM UP problem Corrected threshold energy secondary energy distributions in MF=5 Corrected interpolation in MF=5 |