IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 8.11910+ 4 1.9100E+02 0 0 0 08191 1451 1 0.0000E+00 0.0000E+00 0 0 0 68191 1451 2 1.0000E+00 2.0000E+07 0 0 10 68191 1451 3 0.0000E+00 0.0000E+00 0 0 13 38191 1451 4 81-Tl-191 INPE EVAL-JAN94 GRUDZEVICH,ZELENETSKIJ,PASHCHENKO8191 1451 5 ADL-3 DATA FILE DIST-JAN94 8191 1451 6 ----ADL-3/T MATERIAL 8191 8191 1451 7 -----INCIDENT NEUTRON DATA 8191 1451 8 ------ENDF/B-VI-INT FORMAT 8191 1451 9 -------REFERENCE: 8191 1451 10 THIS VERSION OF ADL-3 LIBRARY IS INTENDED FOR INTEGRAL TESTS ONLY.8191 1451 11 OBNINSK INSTITUTE OF NUCLEAR POWER ENGINEERING, OBNINSK, RUSSIA. 8191 1451 12 ******************************************************************8191 1451 13 ---103---STAPRE 8191 1451 14 OMP:WIL,PER,MCF; RN_SYST (F86;= 2.7640E-01); 8191 1451 15 ---107---STAPRE 8191 1451 16 OMP:WIL,PER,MCF; RN_SYST (F86;= 2.4845E-01) 8191 1451 17 1 451 20 08191 1451 18 3 103 10 08191 1451 19 3 107 10 08191 1451 20 8191 1 099999 8191 0 0 0 8.11910+ 4 1.9100E+02 0 0 0 08191 3103 1 0.0000E+00 5.2900E+06 0 0 1 198191 3103 2 19 2 0 0 0 08191 3103 3 0.0000E+00 0.0000E+00 6.1320E+05 7.4407E-04 1.8798E+06 2.8663E-038191 3103 4 2.7242E+06 5.8693E-03 3.9908E+06 1.3153E-02 4.8352E+06 1.9424E-028191 3103 5 6.1018E+06 2.6604E-02 7.3684E+06 3.0721E-02 8.2128E+06 3.3127E-028191 3103 6 9.4794E+06 3.4480E-02 1.0746E+07 3.6730E-02 1.1590E+07 3.8327E-028191 3103 7 1.2857E+07 3.6614E-02 1.3701E+07 3.3473E-02 1.4968E+07 2.7508E-028191 3103 8 1.6235E+07 2.4296E-02 1.7079E+07 2.2205E-02 1.8346E+07 1.8133E-028191 3103 9 1.9612E+07 1.4648E-02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+008191 3103 10 8191 3 099999 8.11910+ 4 1.9100E+02 0 0 0 08191 3107 1 0.0000E+00 1.1990E+07 0 0 1 208191 3107 2 20 2 0 0 0 08191 3107 3 0.0000E+00 0.0000E+00 7.5390E+05 4.6381E-05 1.7190E+06 2.8477E-048191 3107 4 3.1665E+06 1.2007E-03 4.1315E+06 1.2856E-03 5.0965E+06 1.3483E-038191 3107 5 6.5441E+06 1.4916E-03 7.5091E+06 1.7706E-03 8.4741E+06 2.2205E-038191 3107 6 9.4392E+06 2.7620E-03 1.0887E+07 3.9949E-03 1.1852E+07 5.0045E-038191 3107 7 1.2817E+07 5.7608E-03 1.4264E+07 6.2903E-03 1.5229E+07 6.2268E-038191 3107 8 1.6194E+07 6.3580E-03 1.7642E+07 6.2092E-03 1.8607E+07 5.5677E-038191 3107 9 1.9572E+07 4.8306E-03 2.0537E+07 4.2246E-03 0.0000E+00 0.0000E+008191 3107 10 8191 3 099999 8191 0 0 0 0 0 0 0 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0