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	COMMENTS
1056130	Ba130	JENDL-4.0	(1,451) Updated. (2,151) Updated. (3,1) Re-calculated from partial cross sections. (3,2) Calculated from URP in lower energy range. (3,4) Re-calculated from partial cross sections. (3,102) Calculated from URP in lower energy range.	For JENDL-4.0, the unresolved resonance parameters were re-evaluated by the ASREP /23/ code so as to reproduce the total and capture cross sections given in JENDL3.3 in the energy region from 2.53 keV to 200 keV. The parameters should be used only for self-shielding calculations.							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. Resonance parameters in JENDL-3.3 were revised for JENDL-4. Resonance parameters were based on Mughabghab et al./2/ Neutron orbital angular momentum L was assumed to be 0 for all the resonances. Average radiation width was taken fro Mughabghab et al. and scattering radius was determined fro optical model calculation with CASTHY/3/. A negative resonance was added to so as to reproduce the thermal capture cross section recommended by Mughabghab /22/