IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 8.21920+ 4 1.9200E+02 0 0 0 08292 1451 1 0.0000E+00 0.0000E+00 0 0 0 68292 1451 2 1.0000E+00 2.0000E+07 0 0 10 68292 1451 3 0.0000E+00 0.0000E+00 0 0 13 38292 1451 4 82-Pb-192 INPE EVAL-JAN94 GRUDZEVICH,ZELENETSKIJ,PASHCHENKO8292 1451 5 ADL-3 DATA FILE DIST-JAN94 8292 1451 6 ----ADL-3/T MATERIAL 8292 8292 1451 7 -----INCIDENT NEUTRON DATA 8292 1451 8 ------ENDF/B-VI-INT FORMAT 8292 1451 9 -------REFERENCE: 8292 1451 10 THIS VERSION OF ADL-3 LIBRARY IS INTENDED FOR INTEGRAL TESTS ONLY.8292 1451 11 OBNINSK INSTITUTE OF NUCLEAR POWER ENGINEERING, OBNINSK, RUSSIA. 8292 1451 12 ******************************************************************8292 1451 13 ---103---STAPRE 8292 1451 14 OMP:WIL,PER,MCF; RN_SYST (F86;= 7.3490E-02); 8292 1451 15 ---107---STAPRE 8292 1451 16 OMP:WIL,PER,MCF; RN_SYST (F86;= 8.5592E-02) 8292 1451 17 1 451 20 08292 1451 18 3 103 10 08292 1451 19 3 107 10 08292 1451 20 8292 1 099999 8292 0 0 0 8.21920+ 4 1.9200E+02 0 0 0 08292 3103 1 0.0000E+00 4.1400E+06 0 0 1 198292 3103 2 19 2 0 0 0 08292 3103 3 0.0000E+00 0.0000E+00 5.8300E+05 1.7440E-05 1.8797E+06 3.3100E-048292 3103 4 2.7442E+06 1.1717E-03 4.0409E+06 4.5054E-03 4.9054E+06 9.0017E-038292 3103 5 6.2021E+06 1.9076E-02 7.0666E+06 2.5633E-02 8.3633E+06 3.3585E-028292 3103 6 9.6601E+06 3.7669E-02 1.0525E+07 3.9625E-02 1.1821E+07 4.3839E-028292 3103 7 1.2686E+07 4.4117E-02 1.3982E+07 4.1385E-02 1.4847E+07 3.8161E-028292 3103 8 1.6144E+07 3.4268E-02 1.7008E+07 3.2564E-02 1.8305E+07 2.6822E-028292 3103 9 1.9602E+07 1.9726E-02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+008292 3103 10 8292 3 099999 8.21920+ 4 1.9200E+02 0 0 0 08292 3107 1 0.0000E+00 1.2750E+07 0 0 1 208292 3107 2 20 2 0 0 0 08292 3107 3 0.0000E+00 0.0000E+00 6.1320E+05 3.9457E-04 1.5782E+06 6.3393E-048292 3107 4 3.0257E+06 5.5710E-03 3.9907E+06 9.2042E-03 4.9557E+06 7.6074E-038292 3107 5 5.9207E+06 6.3731E-03 7.3682E+06 5.4877E-03 8.3332E+06 5.5086E-038292 3107 6 9.2982E+06 5.7563E-03 1.0746E+07 6.4461E-03 1.1711E+07 7.3833E-038292 3107 7 1.2676E+07 8.0309E-03 1.3641E+07 8.2959E-03 1.5088E+07 8.0070E-038292 3107 8 1.6053E+07 8.0262E-03 1.7018E+07 7.9198E-03 1.8466E+07 6.6516E-038292 3107 9 1.9431E+07 5.5024E-03 2.0396E+07 4.4487E-03 0.0000E+00 0.0000E+008292 3107 10 8292 3 099999 8292 0 0 0 0 0 0 0 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0