CODE	NUCLIDE	ORIGINAL DATA TAKEN FROM	MODIFICATION	ADDITIONAL FILE MODIFICATIONS	ORIGINAL DATA TAKEN FROM	MODIFICATION	ADDITIONAL FILE MODIFICATIONS	COMMENTS
1048116	048_Cd_116	New evaluation + ENDF/B-VII.0	The remaining part of the evaluation (above the RRR) is the ENDF/B-VII.0 file, which description has been left below intact (including the description of the replaced RRR evaluation in order to be temporarily used for comparison).		ENDF/B-VI MOD 4	Revision (R.Q. Wright, ORNL, V. McLane, NNDC, August 1996) . Added file 1 comments . Unresolved resonance parameters were revised in order to eliminate a discontinuity in total cross section at 100 keV. . The s- and p-wave strength functions are increased to 0.2E-4 and 3.4E-4, respectively. . The scattering radius is increased to 6.50 fm. This revised value is used for both the resolved and the unresolved resonance regions. The calculated resolved resonance thermal scattering cross section is 5.806 barns, in good agreement with the experimental value, 6 +/- 1. The revised evaluation has higher total and elastic cross sections between 9 and 100 keV but the capture is almost identical to the previous evaluation. The differences vary from +1.2 to -2.0%, relative to the previous capture in the ENDF/B-VI, release 2, evaluation.	File obtained by merging: - Resolved Resonances (MLBW) <9.5 keV : Ref.1 - Unresolved Resonances 9.5 keV - 100 keV : ENDF/B-VI - Fast neutron region >100 keV : ENDF/B-VI Resonance parameters were modified: - scattering radius - parameters of a negative resonance Corrected threshold energy secondary energy distributions in MF=5. Reference: 1) S.F.Mughabghab: Atlas of Neutron Resonances, to be published by Elsevier, 2006 (5-th edition of BNL-325)	File produced by WPEC Subgroup 23 in 2004-2005