| 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 |
| 1058144 | 58-Ce-144 | 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 threshold energy secondary energy distributions in MF=5 Corrected interpolation in MF=5 Corrected MF=3, MT=2 at 7.48331, 7.73734, 4.48331, 8.48528 and 8.73885 MeV for SUM UP problem |