Lib: ENDF/B-VII.1 Library: ENDF/B-VII.1 U.S. Evaluated Nuclear Data Library, issued in 2011 Sub-library: NSUB=19 Neutron Cross Section Standards -------------------------------------------------------------------------------- #) MAT Material Lab. Date Authors -------------------------------------------------------------------------------- 1) 125 1-H-1 LANL EVAL-OCT05 G.M.Hale 20.MeV std/std_0125_1-H-1.zip 8Kb 2) 225 2-HE-3 LANL EVAL-MAY90 G.Hale, D.Dodder, P.Young 20.MeV std/std_0225_2-He-3.zip 5Kb 3) 325 3-LI-6 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 2.MeV std/std_0325_3-Li-6.zip 20Kb 4) 525 5-B-10 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 1.MeV std/std_0525_5-B-10.zip 66Kb 5) 600 6-C-0 LANL,ORNL EVAL-JUN96 M.B.Chadwick, P.G.Young, C.Y. Fu 150.MeV std/std_0600_6-C-0.zip 37Kb 6) 7925 79-AU-197 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 2.MeV std/std_7925_79-Au-197.zip 17Kb 7) 9228 92-U-235 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 200.MeV std/std_9228_92-U-235.zip 56Kb 8) 9237 92-U-238 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 200.MeV std/std_9237_92-U-238.zip 23Kb -------------------------------------------------------------------------------- Total: Materials:8 Size:886Kb Compressed:228Kb