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
1059143	Pr143	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, resonance energies and neutron widths were evaluated on the basis of experimental data of Anufriev et al./20/ Average capture width was assumed to be 100 meV. A negative resonance was assumed at -10 eV adjusting its parameters to the capture cross section of 89+-10 b at 0.025 eV/19/. Scattering radius was assumed to be 6.0 fm which was the same as Pr-141. For JENDL-4.0, the unresolved resonance parameters were re-evaluated by the ASREP /21/ code so as to reproduce the total and capture cross sections given in JENDL3.3 in the energy region from 500 eV 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.