CODE	NUCLIDE	ORIGINAL DATA TAKEN FROM	MODIFICATION	ADDITIONAL FILE MODIFICATIONS	ORIGINAL DATA TAKEN FROM	MODIFICATION	ADDITIONAL FILE MODIFICATIONS	COMMENTS
1095241	095_Am_241	ENDF/B-VII.0		P.Young [10/26/06] Modified MF=13,MT=3 continuum x/s following the prescription by H.Trellue and R.Little to correct problems in running MCNPX. Also regridded MF=13,MT=3 summed x/s, added MF=15,MT=3 dummy spectrum at 1.e-5 eV, and corrected gridding problems & inconsistencies between MF=3 and MF=9.	ENDF/B-VI Rev. 2	MF=3 Neutron Cross Sections MT=2 Adjusted to that cross sections sum to total. MT=16,17 GNASH calclautions, and the parameters were adjusted to reproduce the experiemtal data of Lougheed [Lo01], Filatenkov [Fi99], and LANL C-INC data. MT=18 The SOK code was used for evaluating the fission cross section from 6 to 17 MeV. GNASH calculation was adopted at high energies. MT=102 Hauser-Feshbach statistical model calculations, and renormalized to the experimental data of Gayther [Ga77], and Wisshak [Wi80]. MF=9 Multiplicities for production of radioactive elements MT=102 Re-evaluated based on the GNASH calculation and experimental data of Shinohara [Si97], and LANL C-INC. Fi99 A.A. Filatenkov, RI-252, Khlopin Radium Institute (1999). Ga77 D.B. Gayther, B.W. Thomas, Proc. 4th All Union Conf. on Neutron Physics, Kiev, 1977, Vol.3, p.3 (1977). Lo01 R.W. Lougheed, et al., UCRL-ID-145592, LLNL (2001). Si97 N. Shinohara, et al., J. Nucl. Sci. Technol., 34, 7 (1997). Wi80 K. Wisshak, F. Kaeppeler, Nucl. Sci. Eng., 76, 148 (1980).