CODE	NUCLIDE	ORIGINAL DATA TAKEN FROM	MODIFICATION	ADDITIONAL FILE MODIFICATIONS	ORIGINAL DATA TAKEN FROM	MODIFICATION	ADDITIONAL FILE MODIFICATIONS	COMMENTS
1049115	049_In_115	JENDL-3.2	(2,151) UNRESOLVED RESONANCE PARAMETERS RE-ADJUSTED SO AS TO REPRODUCE THE RE-NORMALIZED CAPTURE CROSS SECTION. (3,102) RE-NORMALIZATION. (3,2), (3,4), (3,51-91) AND ANGULAR DISTRIBUTIONS SMALL EFFECTS OF THE RE-NORMALIZATION OF CAPTURE CROSS SECTION.	File obtained by merging: - Resolved Resonances (MLBW) <2. keV : Ref.1 - Unresolved Resonances 2. keV - 100 keV : JENDL-3.3 - Fast neutron region >100 keV : JENDL-3.3 Corrected threshold energy secondary energy distributions in MF=5. Corrected interpolation in MF=5. Reference: 1) S.F.Mughabghab: Atlas of Neutron Resonances, to be published by Elsevier, 2006 (5-th edition of BNL-325) Branching ratio for (n,g)In-116m added in MF 9 (Trkov, July 2011) Value: 0.79 to reproduce the thermal value (recommended by IUPAC for NAA) and Cf-252 spontaneous fission spectrum averaged cross section (evaluated by Mannhart).				File produced by WPEC Subgroup 23 in 2004-2005 JENDL-3.2 data were automatically transformed to JENDL-3.3. Interpolation of spectra: 22 (unit base interpolation) (3,251) deleted, T-matrix of (4,2) deleted, and others.