IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 1.00300+ 3 3.0000E+00 0 0 0 0 103 1451 1 0.0000E+00 0.0000E+00 0 0 0 6 103 1451 2 1.0000E+00 2.0000E+07 0 0 10 6 103 1451 3 0.0000E+00 0.0000E+00 0 0 12 2 103 1451 4 1-H - 3 INPE EVAL-JAN94 GRUDZEVICH,ZELENETSKIJ,PASHCHENKO 103 1451 5 ADL-3 DATA FILE DIST-JAN94 103 1451 6 ----ADL-3/T MATERIAL 103 103 1451 7 -----INCIDENT NEUTRON DATA 103 1451 8 ------ENDF/B-VI-INT FORMAT 103 1451 9 -------REFERENCE: 103 1451 10 THIS VERSION OF ADL-3 LIBRARY IS INTENDED FOR INTEGRAL TESTS ONLY. 103 1451 11 OBNINSK INSTITUTE OF NUCLEAR POWER ENGINEERING, OBNINSK, RUSSIA. 103 1451 12 ****************************************************************** 103 1451 13 --- 16--- EAF-3 103 1451 14 H - 3N,2N 1.0000+00* ENDF/B-V 103 1451 15 COMMENT. N,D IS SAME REACTION 103 1451 16 1 451 18 0 103 1451 17 3 16 13 0 103 1451 18 103 1 099999 103 0 0 0 1.00300+ 3 3.0000E+00 0 0 0 0 103 3 16 1 0.0000E+00-6.2555E+06 0 0 1 29 103 3 16 2 29 2 0 0 0 0 103 3 16 3 8.3228E+06 0.0000E+00 8.3800E+06 1.0000E-03 8.4000E+06 2.5000E-03 103 3 16 4 8.5000E+06 6.5000E-03 8.6000E+06 1.1500E-02 8.7500E+06 1.6500E-02 103 3 16 5 9.0000E+06 2.4000E-02 9.2500E+06 3.1000E-02 9.5000E+06 3.5500E-02 103 3 16 6 1.0000E+07 4.4500E-02 1.0250E+07 4.7500E-02 1.0500E+07 4.9500E-02 103 3 16 7 1.0750E+07 5.0700E-02 1.1000E+07 5.1600E-02 1.1300E+07 5.2200E-02 103 3 16 8 1.1500E+07 5.2500E-02 1.2000E+07 5.2500E-02 1.2500E+07 5.2200E-02 103 3 16 9 1.3000E+07 5.1600E-02 1.3500E+07 5.0900E-02 1.4000E+07 5.0000E-02 103 3 16 10 1.4100E+07 4.9700E-02 1.4500E+07 4.8800E-02 1.5000E+07 4.7600E-02 103 3 16 11 1.5500E+07 4.6400E-02 1.6000E+07 4.5000E-02 1.7500E+07 4.0800E-02 103 3 16 12 1.9400E+07 3.5600E-02 2.0000E+07 3.3800E-02 0.0000E+00 0.0000E+00 103 3 16 13 103 3 099999 103 0 0 0 0 0 0 0 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0