Lib:         ENDF/B-VII.0
 Library:     ENDF/B-VII.0 U.S. Evaluated Nuclear Data Library, issued in 2006
 Sub-library: NSUB=19      Neutron Cross Section Standards
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   #)  MAT Material     Lab.         Date         Authors
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   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
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Total: Materials:8 Size:886Kb Zipped:228Kb