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
1058141 58-Ce-141 ENDF/B-VII New MF=6 MT=102 taken from TENDL2011 (Replaces any existing Data) / / / / / / / / File obtained by merging: Resolved Resonances (MLBW) <350 eV : Ref.1 Unresolved Resonances 350 eV - 100 keV : CENDL 3 Fast neutron region >100 keV : CENDL 3 Ref.1 : S.F.Mughabghab: Atlas of Neutron Resonances, to be published by Elsevier, 2006 (5-th edition of BNL-325) Corrected threshold energy secondary energy distributions in MF=5 Corrected MF=3, MT=2 at 7.23762, 7.48331, and 8.48528 MeV for SUM UP problem