IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 7.81780+ 4 1.7800E+02 0 0 0 07878 1451 1 0.0000E+00 0.0000E+00 0 0 0 67878 1451 2 1.0000E+00 2.0000E+07 0 0 10 67878 1451 3 0.0000E+00 0.0000E+00 0 0 13 37878 1451 4 78-Pt-178 INPE EVAL-JAN94 GRUDZEVICH,ZELENETSKIJ,PASHCHENKO7878 1451 5 ADL-3 DATA FILE DIST-JAN94 7878 1451 6 ----ADL-3/T MATERIAL 7878 7878 1451 7 -----INCIDENT NEUTRON DATA 7878 1451 8 ------ENDF/B-VI-INT FORMAT 7878 1451 9 -------REFERENCE: 7878 1451 10 THIS VERSION OF ADL-3 LIBRARY IS INTENDED FOR INTEGRAL TESTS ONLY.7878 1451 11 OBNINSK INSTITUTE OF NUCLEAR POWER ENGINEERING, OBNINSK, RUSSIA. 7878 1451 12 ******************************************************************7878 1451 13 ---103---STAPRE 7878 1451 14 OMP:WIL,PER,MCF; RN_SYST (F86;= 1.2512E-01); 7878 1451 15 ---107---STAPRE 7878 1451 16 OMP:WIL,PER,MCF; RN_SYST (F86;= 8.2000E-02) 7878 1451 17 1 451 20 07878 1451 18 3 103 10 07878 1451 19 3 107 10 07878 1451 20 7878 1 099999 7878 0 0 0 7.81780+ 4 1.7800E+02 0 0 0 07878 3103 1 0.0000E+00 5.0700E+06 0 0 1 197878 3103 2 19 2 0 0 0 07878 3103 3 0.0000E+00 0.0000E+00 4.9280E+05 1.9968E-03 1.8202E+06 1.3209E-027878 3103 4 2.7051E+06 3.3287E-02 4.0325E+06 8.5335E-02 4.9175E+06 1.3154E-017878 3103 5 6.2449E+06 1.9371E-01 7.1298E+06 2.1572E-01 8.4572E+06 2.3124E-017878 3103 6 9.3422E+06 2.2675E-01 1.0670E+07 2.0484E-01 1.1555E+07 1.8562E-017878 3103 7 1.2882E+07 1.4610E-01 1.3767E+07 1.1600E-01 1.5094E+07 7.4079E-027878 3103 8 1.5979E+07 5.4038E-02 1.7307E+07 3.3425E-02 1.8192E+07 2.4157E-027878 3103 9 1.9519E+07 1.5269E-02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+007878 3103 10 7878 3 099999 7.81780+ 4 1.7800E+02 0 0 0 07878 3107 1 0.0000E+00 1.3590E+07 0 0 1 207878 3107 2 20 2 0 0 0 07878 3107 3 0.0000E+00 0.0000E+00 1.1464E+06 3.4405E-03 2.1520E+06 1.3822E-027878 3107 4 3.1576E+06 2.4538E-02 4.1633E+06 2.6852E-02 5.1689E+06 2.6307E-027878 3107 5 6.6773E+06 2.5325E-02 7.6829E+06 2.5070E-02 8.6885E+06 2.5625E-027878 3107 6 9.6942E+06 2.5790E-02 1.0700E+07 2.5722E-02 1.2208E+07 2.5397E-027878 3107 7 1.3214E+07 2.4250E-02 1.4219E+07 2.2059E-02 1.5225E+07 1.8808E-027878 3107 8 1.6231E+07 1.5642E-02 1.7739E+07 1.0999E-02 1.8745E+07 8.2629E-037878 3107 9 1.9750E+07 6.0600E-03 2.0756E+07 4.4267E-03 0.0000E+00 0.0000E+007878 3107 10 7878 3 099999 7878 0 0 0 0 0 0 0 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0