CODE | NUCLIDE | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | COMMENTS |
1059141 | 059_Pr_141 | ENDF/B-VII | 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 |