CODE | NUCLIDE | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | ORIGINAL DATA TAKEN FROM | MODIFICATION | ADDITIONAL FILE MODIFICATIONS | COMMENTS |
1035079 | 035_Br_079 | CONVERTED FROM JENDL-3.3 | Corrected MF=3, MT=2 at 9.48683 and 11.4891 MeV for SUM UP problem Corrected threshold energy secondary energy distributions in MF=5. Corrected interpolation in MF=5. |
JENDL-3.2 | (2,151) UNRESOLVED RESONANCE PARAMETERS RE-ADJUSTED SO AS TO REPRODUCE THE RE-NORMALIZED CAPTURE CROSS SECTION. (3,102) RE-NORMALIZED. (3,4), (3,51-91) AND ANGULAR DISTRIBUTIONS SMALL EFFECTS OF THE RE-NORMALIZATION OF THE CAPTURE CROSS SECTION. |
File produced by WPEC Subgroup 23 in 2004-2005 CONVERTED FROM JENDL-3.3 BY NNDC OCT 2004 |