CODE	NUCLIDE	ORIGINAL DATA TAKEN FROM	MODIFICATION	ADDITIONAL FILE MODIFICATIONS	ORIGINAL DATA TAKEN FROM	MODIFICATION	ADDITIONAL FILE MODIFICATIONS	COMMENTS
1095242	095_Am_242	ENDF/B-VII.0	T. Kawano, M.B. Chadwick, A. Kahler, P.G. Young [Oct. 2010, Aug. 2011] MF=2 Resonance Parameters ENDF/B-VII.0 resonance parameters (were from ENDF/B-VI) were replaced by the JENDL-4 resonance parameters. The energies of resolved resonances are almost identical to the values in ENDF/B-VI, but spins and widths show some differences. In the unresolved resonance range, we adopted LSSF=1, so that the dilute cross sections are now given in File 3. MF=3 Neutron Cross Sections MT=18 We performed a SOK analysis in the entire energy range to obtain both the cross sections and its covariance. The energy boundary was lowered to 150 eV. The subthreshold cross sections are now given in File 3. MT=102 The capture cross section was re-evaluated with the Hauser-Feshbach calculations (CoH3), which reproduces the DANCE experimental data and an integral measuremnt. MF=32 Resonance Parameter Covariance Take from JENDL-4, as for the resonance parameters. MF=33 Neutron Cross Section Covariances The covariance matrices for the total, inelastic, (n,2n), (n,3n), (n,4n), and capture cross sections were calculated with KALMAN, combining the statistical model calculations with available experimental data. The covariance matrix for the fission cross section was obtained with the SOK code.		New evaluation + JENDL-3.3	At low incident neutron energies, the resonance parameters were directly taken from the JENDL-3.3 evaluation file. The sections MF1,MT452,455,456 and MF5,MT18 were also adopted from the JENDL-3.3 evaluation.		AUG11 Added MT458 fission energy release data based on R. Vogt Energy-Dependent Fission Q Values Generalized for All Actinides Oct 8, 2008 report LLNL-TR-407620