 7.716400+4 1.625830+2         -1          0          2          12824 1451    1
 2.700000+5 1.000000+0          1          1          0          62824 1451    2
 0.000000+0 0.000000+0          0          0          4        3112824 1451    3
 0.000000+0 0.000000+0          0          0         18          22824 1451    4
 77-Ir-164MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2824 1451    5
                      DIST-NOV07                       261107     2824 1451    6
----JEFF-311          MATERIAL 2824                               2824 1451    7
-----RADIOACTIVE DECAY DATA                                       2824 1451    8
------ENDF-6 FORMAT                                               2824 1451    9
******************************************************************2824 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2824 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2824 1451   12
**             Original data taken from:  NUBASE                **2824 1451   13
******************************************************************2824 1451   14
******************************************************************2824 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2824 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2824 1451   17
                                                                  2824 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2824 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2824 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2824 1451   21
******************************************************************2824 1451   22
                                1        451         24          02824 1451   23
                                8        457          7          02824 1451   24
 0.000000+0 0.000000+0          0          0          0          02824 1  099999
                                                                  2824 0  0    0
 7.71640+04 1.62583+02          1          1          0          02824 8457    1
 9.40000-05 2.70000-05          0          0          6          02824 8457    2
 1.49556+06 0.00000+00 1.49556+06 0.00000+00 3.02203+06 0.00000+002824 8457    3
 9.00000+00 1.00000+00          0          0         18          32824 8457    4
 7.00000+00 0.00000+00 1.83100+06 0.00000+00 3.33333-01 0.00000+002824 8457    5
 4.00000+00 0.00000+00 7.23510+06 0.00000+00 3.33333-01 0.00000+002824 8457    6
 2.00000+00 0.00000+00 1.34600+07 0.00000+00 3.33333-01 0.00000+002824 8457    7
                                                                  2824 8  099999
                                                                  2824 0  0    0
                                                                     0 0  0    0
 7.716500+4 1.635700+2         -1          0          2          12825 1451    1
 0.000000+0 1.000000+0          0          0          0          62825 1451    2
 0.000000+0 0.000000+0          0          0          4        3112825 1451    3
 0.000000+0 0.000000+0          0          0         18          22825 1451    4
 77-Ir-165 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2825 1451    5
                      DIST-NOV07                       261107     2825 1451    6
----JEFF-311          MATERIAL 2825                               2825 1451    7
-----RADIOACTIVE DECAY DATA                                       2825 1451    8
------ENDF-6 FORMAT                                               2825 1451    9
******************************************************************2825 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2825 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2825 1451   12
**             Original data taken from:  NUBASE                **2825 1451   13
******************************************************************2825 1451   14
******************************************************************2825 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2825 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2825 1451   17
                                                                  2825 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2825 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2825 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2825 1451   21
******************************************************************2825 1451   22
                                1        451         24          02825 1451   23
                                8        457          6          02825 1451   24
 0.000000+0 0.000000+0          0          0          0          02825 1  099999
                                                                  2825 0  0    0
 7.71650+04 1.63570+02          0          0          0          02825 8457    1
 1.00000-06 0.00000+00          0          0          6          02825 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 4.18305+06 0.00000+002825 8457    3
 5.00000-01 1.00000+00          0          0         12          22825 8457    4
 7.00000+00 0.00000+00 1.54100+06 0.00000+00 5.00000-01 0.00000+002825 8457    5
 4.00000+00 0.00000+00 6.82510+06 0.00000+00 5.00000-01 0.00000+002825 8457    6
                                                                  2825 8  099999
                                                                  2825 0  0    0
                                                                     0 0  0    0
 7.716600+4 1.645600+2         -1          0          2          12826 1451    1
 0.000000+0 1.000000+0          0          0          0          62826 1451    2
 0.000000+0 0.000000+0          0          0          4        3112826 1451    3
 0.000000+0 0.000000+0          0          0         74          22826 1451    4
 77-Ir-166 ENSDF      EVAL-SEP99 CONVERSION OF ENSDF              2826 1451    5
 /ENSDF/              DIST-NOV07                       261107     2826 1451    6
----JEFF-311          MATERIAL 2826                               2826 1451    7
-----RADIOACTIVE DECAY DATA                                       2826 1451    8
------ENDF-6 FORMAT                                               2826 1451    9
******************************************************************2826 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2826 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2826 1451   12
**             Original data taken from:  ENSDF                 **2826 1451   13
******************************************************************2826 1451   14
******************************************************************2826 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2826 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2826 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2826 1451   18
******************************************************************2826 1451   19
166IR DECAY 10.5 MS  22      COMBINED DATA  I(min) = 0.0E+00 %    2826 1451   20
         Ex = 0           keV                     2 decay mode(s) 2826 1451   21
                                                                  2826 1451   22
166IR A DECAY               Q =  6724.0000 keV       6.0000       2826 1451   23
         Branching                 93.1000 %         2.9000       2826 1451   24
                         Br*Q =  6260.0440 keV     195.0760       2826 1451   25
                                              0 isomeric state(s) 2826 1451   26
                                                                  2826 1451   27
         Mean alpha    energy    6109.2220 keV       5.5860       2826 1451   28
         Mean beta     energy       0.0000 keV       0.0000       2826 1451   29
         Mean conv. e- energy       0.0000 keV       0.0000       2826 1451   30
         Mean Auger e- energy       0.0000 keV       0.0000       2826 1451   31
         Mean gamma    energy       0.0000 keV                    2826 1451   32
         Mean X        energy       0.0000 keV       0.0000       2826 1451   33
         Mean recoil   energy     151.2374 keV       0.1383       2826 1451   34
         Mean neutrino energy       0.0000 keV       0.0000       2826 1451   35
         Mean neutron  energy       0.0000 keV       0.0000       2826 1451   36
         Total         energy    6260.4594 keV       5.5877       2826 1451   37
         Q effective             6260.0440 keV     195.0760       2826 1451   38
         diff. mode                 0.4154 keV       0.0066 %     2826 1451   39
                                                                  2826 1451   40
         Mean e- bind. energy       0.0000 keV                    2826 1451   41
         diff. atomic               0.0000 keV       0.0000 %     2826 1451   42
         diff. nuclear              0.4154 keV       0.0066 %     2826 1451   43
                                                                  2826 1451   44
166IR P DECAY               Q =  1168.0000 keV       8.0000       2826 1451   45
         Branching                  6.9000 %         2.9000       2826 1451   46
                         Br*Q =    80.5920 keV      33.8765       2826 1451   47
                                              0 isomeric state(s) 2826 1451   48
                                                                  2826 1451   49
         Mean alpha    energy       0.0000 keV       0.0000       2826 1451   50
         Mean beta     energy       0.0000 keV       0.0000       2826 1451   51
         Mean conv. e- energy       0.0000 keV       0.0000       2826 1451   52
         Mean Auger e- energy       0.0000 keV       0.0000       2826 1451   53
         Mean gamma    energy       0.0000 keV                    2826 1451   54
         Mean X        energy       0.0000 keV       0.0000       2826 1451   55
         Mean recoil   energy       0.4832 keV       0.0034       2826 1451   56
         Mean neutrino energy       0.0000 keV       0.0000       2826 1451   57
         Mean neutron  energy       0.0000 keV       0.0000       2826 1451   58
         Total         energy      79.4882 keV       0.5520       2826 1451   59
         Q effective               80.5920 keV      33.8765       2826 1451   60
         diff. mode                -1.1038 keV      -1.3696 %     2826 1451   61
                                                                  2826 1451   62
         Mean e- bind. energy       0.0000 keV                    2826 1451   63
         diff. atomic               0.0000 keV       0.0000 %     2826 1451   64
         diff. nuclear             -1.1038 keV      -1.3696 %     2826 1451   65
                                                                  2826 1451   66
166IR TOTAL DECAY                                                 2826 1451   67
         Mean alpha    energy    6109.2220 keV       5.5860       2826 1451   68
         Mean beta     energy       0.0000 keV       0.0000       2826 1451   69
         Mean CE+Auger energy       0.0000 keV       0.0000       2826 1451   70
         Mean gamma+X  energy       0.0000 keV       0.0000       2826 1451   71
         Mean recoil   energy     151.7206 keV       0.1383       2826 1451   72
         Mean neutrino energy       0.0000 keV       0.0000       2826 1451   73
         Mean neutron  energy       0.0000 keV       0.0000       2826 1451   74
         Total         energy    6339.9476 keV       5.6149       2826 1451   75
         Q effective             6340.6360 keV     197.9956       2826 1451   76
         diff.                     -0.6884 keV      -0.0109 %     2826 1451   77
                                                                  2826 1451   78
                                1        451         80          02826 1451   79
                                8        457         10          02826 1451   80
 0.000000+0 0.000000+0          0          0          0          02826 1  099999
                                                                  2826 0  0    0
 7.71660+04 1.64560+02          0          0          0          12826 8457    1
 1.05000-02 2.20000-03          0          0          6          02826 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 6.26094+06 5.58771+032826 8457    3
 2.00000+00-1.00000+00          0          0         12          22826 8457    4
 4.00000+00 0.00000+00 6.72400+06 6.00000+03 9.31000-01 2.90000-022826 8457    5
 7.00000+00 0.00000+00 1.16800+06 8.00000+03 6.90000-02 2.90000-022826 8457    6
 0.00000+00 4.00000+00          0          0          6          12826 8457    7
 1.00000-02 0.00000+00 6.10922+06 5.58600+03 0.00000+00 0.00000+002826 8457    8
 6.56200+06 6.00000+03          0          0          6          02826 8457    9
 4.00000+00 0.00000+00 9.31000+01 2.90000+00 0.00000+00 0.00000+002826 8457   10
                                                                  2826 8  099999
                                                                  2826 0  0    0
                                                                     0 0  0    0
 7.716600+4 1.645600+2         -1          0          2          12827 1451    1
 1.720000+5 1.000000+0          1          1          0          62827 1451    2
 0.000000+0 0.000000+0          0          0          4        3112827 1451    3
 0.000000+0 0.000000+0          0          0         18          22827 1451    4
 77-Ir-166MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2827 1451    5
                      DIST-NOV07                       261107     2827 1451    6
----JEFF-311          MATERIAL 2827                               2827 1451    7
-----RADIOACTIVE DECAY DATA                                       2827 1451    8
------ENDF-6 FORMAT                                               2827 1451    9
******************************************************************2827 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2827 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2827 1451   12
**             Original data taken from:  NUBASE                **2827 1451   13
******************************************************************2827 1451   14
******************************************************************2827 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2827 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2827 1451   17
                                                                  2827 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2827 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2827 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2827 1451   21
******************************************************************2827 1451   22
                                1        451         24          02827 1451   23
                                8        457          6          02827 1451   24
 0.000000+0 0.000000+0          0          0          0          02827 1  099999
                                                                  2827 0  0    0
 7.71660+04 1.64560+02          1          1          0          02827 8457    1
 1.51000-02 9.00000-04          0          0          6          02827 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 6.61706+06 0.00000+002827 8457    3
 9.00000+00 1.00000+00          0          0         12          22827 8457    4
 4.00000+00 1.00000+00 6.71410+06 0.00000+00 9.82000-01 0.00000+002827 8457    5
 7.00000+00 0.00000+00 1.32300+06 0.00000+00 1.80000-02 0.00000+002827 8457    6
                                                                  2827 8  099999
                                                                  2827 0  0    0
                                                                     0 0  0    0
 7.716700+4 1.655470+2         -1          0          2          12828 1451    1
 0.000000+0 1.000000+0          0          0          0          62828 1451    2
 0.000000+0 0.000000+0          0          0          4        3112828 1451    3
 0.000000+0 0.000000+0          0          0         18          22828 1451    4
 77-Ir-167 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2828 1451    5
                      DIST-NOV07                       261107     2828 1451    6
----JEFF-311          MATERIAL 2828                               2828 1451    7
-----RADIOACTIVE DECAY DATA                                       2828 1451    8
------ENDF-6 FORMAT                                               2828 1451    9
******************************************************************2828 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2828 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2828 1451   12
**             Original data taken from:  NUBASE                **2828 1451   13
******************************************************************2828 1451   14
******************************************************************2828 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2828 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2828 1451   17
                                                                  2828 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2828 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2828 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2828 1451   21
******************************************************************2828 1451   22
                                1        451         24          02828 1451   23
                                8        457          7          02828 1451   24
 0.000000+0 0.000000+0          0          0          0          02828 1  099999
                                                                  2828 0  0    0
 7.71670+04 1.65547+02          0          0          0          02828 8457    1
 3.52000-02 2.00000-03          0          0          6          02828 8457    2
 6.28067+05 0.00000+00 6.28067+05 0.00000+00 3.46389+06 0.00000+002828 8457    3
 5.00000-01 1.00000+00          0          0         18          32828 8457    4
 4.00000+00 0.00000+00 6.50310+06 0.00000+00 4.80000-01 0.00000+002828 8457    5
 7.00000+00 0.00000+00 1.07000+06 0.00000+00 3.20000-01 0.00000+002828 8457    6
 2.00000+00 0.00000+00 9.42100+06 0.00000+00 2.00000-01 0.00000+002828 8457    7
                                                                  2828 8  099999
                                                                  2828 0  0    0
                                                                     0 0  0    0
 7.716700+4 1.655470+2         -1          0          2          12829 1451    1
 1.753000+5 1.000000+0          1          1          0          62829 1451    2
 0.000000+0 0.000000+0          0          0          4        3112829 1451    3
 0.000000+0 0.000000+0          0          0         18          22829 1451    4
 77-Ir-167MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2829 1451    5
                      DIST-NOV07                       261107     2829 1451    6
----JEFF-311          MATERIAL 2829                               2829 1451    7
-----RADIOACTIVE DECAY DATA                                       2829 1451    8
------ENDF-6 FORMAT                                               2829 1451    9
******************************************************************2829 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2829 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2829 1451   12
**             Original data taken from:  NUBASE                **2829 1451   13
******************************************************************2829 1451   14
******************************************************************2829 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2829 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2829 1451   17
                                                                  2829 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2829 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2829 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2829 1451   21
******************************************************************2829 1451   22
                                1        451         24          02829 1451   23
                                8        457          7          02829 1451   24
 0.000000+0 0.000000+0          0          0          0          02829 1  099999
                                                                  2829 0  0    0
 7.71670+04 1.65547+02          1          1          0          02829 8457    1
 3.00000-02 6.00000-04          0          0          6          02829 8457    2
 6.26958+05 0.00000+00 6.26958+05 0.00000+00 5.25570+06 0.00000+002829 8457    3
 5.50000+00-1.00000+00          0          0         18          32829 8457    4
 4.00000+00 1.00000+00 6.56340+06 0.00000+00 8.00000-01 0.00000+002829 8457    5
 2.00000+00 0.00000+00 9.59630+06 0.00000+00 1.96000-01 0.00000+002829 8457    6
 7.00000+00 0.00000+00 1.24530+06 0.00000+00 4.00000-03 0.00000+002829 8457    7
                                                                  2829 8  099999
                                                                  2829 0  0    0
                                                                     0 0  0    0
 7.716800+4 1.665370+2         -1          0          2          12830 1451    1
 0.000000+0 1.000000+0          0          0          0          62830 1451    2
 0.000000+0 0.000000+0          0          0          4        3112830 1451    3
 0.000000+0 0.000000+0          0          0         18          22830 1451    4
 77-Ir-168 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2830 1451    5
                      DIST-NOV07                       261107     2830 1451    6
----JEFF-311          MATERIAL 2830                               2830 1451    7
-----RADIOACTIVE DECAY DATA                                       2830 1451    8
------ENDF-6 FORMAT                                               2830 1451    9
******************************************************************2830 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2830 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2830 1451   12
**             Original data taken from:  NUBASE                **2830 1451   13
******************************************************************2830 1451   14
******************************************************************2830 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2830 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2830 1451   17
                                                                  2830 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2830 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2830 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2830 1451   21
******************************************************************2830 1451   22
                                1        451         24          02830 1451   23
                                8        457          5          02830 1451   24
 0.000000+0 0.000000+0          0          0          0          02830 1  099999
                                                                  2830 0  0    0
 7.71680+04 1.66537+02          0          0          0          02830 8457    1
 1.61000-01 2.10000-02          0          0          6          02830 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 6.47510+06 0.00000+002830 8457    3
-7.77770+01 0.00000+00          0          0          6          12830 8457    4
 4.00000+00 0.00000+00 6.47510+06 0.00000+00 1.00000+00 0.00000+002830 8457    5
                                                                  2830 8  099999
                                                                  2830 0  0    0
                                                                     0 0  0    0
 7.716800+4 1.665370+2         -1          0          2          12831 1451    1
 1.500000+5 1.000000+0          1          1          0          62831 1451    2
 0.000000+0 0.000000+0          0          0          4        3112831 1451    3
 0.000000+0 0.000000+0          0          0         18          22831 1451    4
 77-Ir-168MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2831 1451    5
                      DIST-NOV07                       261107     2831 1451    6
----JEFF-311          MATERIAL 2831                               2831 1451    7
-----RADIOACTIVE DECAY DATA                                       2831 1451    8
------ENDF-6 FORMAT                                               2831 1451    9
******************************************************************2831 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2831 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2831 1451   12
**             Original data taken from:  NUBASE                **2831 1451   13
******************************************************************2831 1451   14
******************************************************************2831 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2831 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2831 1451   17
                                                                  2831 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2831 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2831 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2831 1451   21
******************************************************************2831 1451   22
                                1        451         24          02831 1451   23
                                8        457          6          02831 1451   24
 0.000000+0 0.000000+0          0          0          0          02831 1  099999
                                                                  2831 0  0    0
 7.71680+04 1.66537+02          1          1          0          02831 8457    1
 1.25000-01 4.00000-02          0          0          6          02831 8457    2
 1.90017+06 0.00000+00 1.90017+06 0.00000+00 3.20255+06 0.00000+002831 8457    3
-7.77770+01 0.00000+00          0          0         12          22831 8457    4
 4.00000+00 1.00000+00 6.40510+06 0.00000+00 5.00000-01 0.00000+002831 8457    5
 2.00000+00 0.00000+00 1.14010+07 0.00000+00 5.00000-01 0.00000+002831 8457    6
                                                                  2831 8  099999
                                                                  2831 0  0    0
                                                                     0 0  0    0
 7.716900+4 1.675250+2         -1          0          2          12832 1451    1
 0.000000+0 1.000000+0          0          0          0          62832 1451    2
 0.000000+0 0.000000+0          0          0          4        3112832 1451    3
 0.000000+0 0.000000+0          0          0         40          22832 1451    4
 77-Ir-169 ENSDF      EVAL-OCT94 CONVERSION OF ENSDF              2832 1451    5
 /ENSDF/              DIST-NOV07                       261107     2832 1451    6
----JEFF-311          MATERIAL 2832                               2832 1451    7
-----RADIOACTIVE DECAY DATA                                       2832 1451    8
------ENDF-6 FORMAT                                               2832 1451    9
******************************************************************2832 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2832 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2832 1451   12
**             Original data taken from:  ENSDF                 **2832 1451   13
******************************************************************2832 1451   14
******************************************************************2832 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2832 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2832 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2832 1451   18
******************************************************************2832 1451   19
169IR DECAY 0.4 S     1                     I(min) = 0.0E+00 %    2832 1451   20
         Ex = 0.0         keV                     1 decay mode(s) 2832 1451   21
                                                                  2832 1451   22
169IR A DECAY               Q =  6275.0000 keV      50.0000       2832 1451   23
         Branching                100.0000 %         0.0000       2832 1451   24
                         Br*Q =  6275.0000 keV      50.0000       2832 1451   25
                                              0 isomeric state(s) 2832 1451   26
                                                                  2832 1451   27
         Mean alpha    energy    6126.0000 keV       5.0000       2832 1451   28
         Mean beta     energy       0.0000 keV       0.0000       2832 1451   29
         Mean conv. e- energy       0.0000 keV       0.0000       2832 1451   30
         Mean Auger e- energy       0.0000 keV       0.0000       2832 1451   31
         Mean gamma    energy       0.0000 keV                    2832 1451   32
         Mean X        energy       0.0000 keV       0.0000       2832 1451   33
         Mean recoil   energy     148.8806 keV       0.1215       2832 1451   34
         Mean neutrino energy       0.0000 keV       0.0000       2832 1451   35
         Mean neutron  energy       0.0000 keV       0.0000       2832 1451   36
         Total         energy    6274.8806 keV       5.0015       2832 1451   37
         Q effective             6275.0000 keV      50.0000       2832 1451   38
         diff. mode                -0.1194 keV      -0.0019 %     2832 1451   39
                                                                  2832 1451   40
         Mean e- bind. energy       0.0000 keV                    2832 1451   41
         diff. atomic               0.0000 keV       0.0000 %     2832 1451   42
         diff. nuclear             -0.1194 keV      -0.0019 %     2832 1451   43
                                                                  2832 1451   44
                                1        451         46          02832 1451   45
                                8        457          9          02832 1451   46
 0.000000+0 0.000000+0          0          0          0          02832 1  099999
                                                                  2832 0  0    0
 7.71690+04 1.67525+02          0          0          0          12832 8457    1
 4.00000-01 1.00000-01          0          0          6          02832 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 6.27488+06 5.00148+032832 8457    3
 5.00000-01 1.00000+00          0          0          6          12832 8457    4
 4.00000+00 0.00000+00 6.27500+06 5.00000+04 1.00000+00 0.00000+002832 8457    5
 0.00000+00 4.00000+00          0          0          6          12832 8457    6
 1.00000-02 0.00000+00 6.12600+06 5.00000+03 0.00000+00 0.00000+002832 8457    7
 6.12600+06 5.00000+03          0          0          6          02832 8457    8
 4.00000+00 0.00000+00 1.00000+02 0.00000+00 0.00000+00 0.00000+002832 8457    9
                                                                  2832 8  099999
                                                                  2832 0  0    0
                                                                     0 0  0    0
 7.716900+4 1.675250+2         -1          0          2          12833 1451    1
 1.540000+5 1.000000+0          1          1          0          62833 1451    2
 0.000000+0 0.000000+0          0          0          4        3112833 1451    3
 0.000000+0 0.000000+0          0          0         18          22833 1451    4
 77-Ir-169MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2833 1451    5
                      DIST-NOV07                       261107     2833 1451    6
----JEFF-311          MATERIAL 2833                               2833 1451    7
-----RADIOACTIVE DECAY DATA                                       2833 1451    8
------ENDF-6 FORMAT                                               2833 1451    9
******************************************************************2833 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2833 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2833 1451   12
**             Original data taken from:  NUBASE                **2833 1451   13
******************************************************************2833 1451   14
******************************************************************2833 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2833 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2833 1451   17
                                                                  2833 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2833 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2833 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2833 1451   21
******************************************************************2833 1451   22
                                1        451         24          02833 1451   23
                                8        457          6          02833 1451   24
 0.000000+0 0.000000+0          0          0          0          02833 1  099999
                                                                  2833 0  0    0
 7.71690+04 1.67525+02          1          1          0          02833 8457    1
 3.08000-01 2.20000-02          0          0          6          02833 8457    2
 8.20773+05 0.00000+00 8.20773+05 0.00000+00 4.50583+06 0.00000+002833 8457    3
 5.50000+00-1.00000+00          0          0         12          22833 8457    4
 4.00000+00 1.00000+00 6.25810+06 0.00000+00 7.20000-01 0.00000+002833 8457    5
 2.00000+00 0.00000+00 8.79400+06 0.00000+00 2.80000-01 0.00000+002833 8457    6
                                                                  2833 8  099999
                                                                  2833 0  0    0
                                                                     0 0  0    0
 7.717000+4 1.685150+2         -1          0          2          12834 1451    1
 0.000000+0 1.000000+0          0          0          0          62834 1451    2
 0.000000+0 0.000000+0          0          0          4        3112834 1451    3
 0.000000+0 0.000000+0          0          0         18          22834 1451    4
 77-Ir-170 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2834 1451    5
                      DIST-NOV07                       261107     2834 1451    6
----JEFF-311          MATERIAL 2834                               2834 1451    7
-----RADIOACTIVE DECAY DATA                                       2834 1451    8
------ENDF-6 FORMAT                                               2834 1451    9
******************************************************************2834 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2834 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2834 1451   12
**             Original data taken from:  NUBASE                **2834 1451   13
******************************************************************2834 1451   14
******************************************************************2834 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2834 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2834 1451   17
                                                                  2834 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2834 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2834 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2834 1451   21
******************************************************************2834 1451   22
                                1        451         24          02834 1451   23
                                8        457          7          02834 1451   24
 0.000000+0 0.000000+0          0          0          0          02834 1  099999
                                                                  2834 0  0    0
 7.71700+04 1.68515+02          0          0          0          02834 8457    1
 9.10000-01 1.50000-01          0          0          6          02834 8457    2
 3.35213+06 0.00000+00 3.35213+06 0.00000+00 3.10965+05 0.00000+002834 8457    3
-7.77770+01 0.00000+00          0          0         18          32834 8457    4
 2.00000+00 0.00000+00 1.06080+07 0.00000+00 9.48000-01 0.00000+002834 8457    5
 4.00000+00 0.00000+00 6.10510+06 0.00000+00 2.60000-02 0.00000+002834 8457    6
 4.00000+00 1.00000+00 5.85510+06 0.00000+00 2.60000-02 0.00000+002834 8457    7
                                                                  2834 8  099999
                                                                  2834 0  0    0
                                                                     0 0  0    0
 7.717000+4 1.685150+2         -1          0          2          12835 1451    1
 3.707000+5 1.000000+0          1          1          0          62835 1451    2
 0.000000+0 0.000000+0          0          0          4        3112835 1451    3
 0.000000+0 0.000000+0          0          0         18          22835 1451    4
 77-Ir-170MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2835 1451    5
                      DIST-NOV07                       261107     2835 1451    6
----JEFF-311          MATERIAL 2835                               2835 1451    7
-----RADIOACTIVE DECAY DATA                                       2835 1451    8
------ENDF-6 FORMAT                                               2835 1451    9
******************************************************************2835 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2835 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2835 1451   12
**             Original data taken from:  NUBASE                **2835 1451   13
******************************************************************2835 1451   14
******************************************************************2835 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2835 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2835 1451   17
                                                                  2835 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2835 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2835 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2835 1451   21
******************************************************************2835 1451   22
                                1        451         24          02835 1451   23
                                8        457          8          02835 1451   24
 0.000000+0 0.000000+0          0          0          0          02835 1  099999
                                                                  2835 0  0    0
 7.71700+04 1.68515+02          1          1          0          02835 8457    1
 4.40000-01 6.00000-02          0          0          6          02835 8457    2
 1.17106+06 0.00000+00 1.28969+06 0.00000+00 2.28629+06 0.00000+002835 8457    3
-7.77770+01 0.00000+00          0          0         24          42835 8457    4
 4.00000+00 0.00000+00 6.47580+06 0.00000+00 1.80000-01 0.00000+002835 8457    5
 4.00000+00 1.00000+00 6.22580+06 0.00000+00 1.80000-01 0.00000+002835 8457    6
 2.00000+00 0.00000+00 1.09787+07 0.00000+00 3.20000-01 0.00000+002835 8457    7
 3.00000+00 0.00000+00 3.70700+05 0.00000+00 3.20000-01 0.00000+002835 8457    8
                                                                  2835 8  099999
                                                                  2835 0  0    0
                                                                     0 0  0    0
 7.717100+4 1.695030+2         -1          0          2          12836 1451    1
 0.000000+0 1.000000+0          0          0          0          62836 1451    2
 0.000000+0 0.000000+0          0          0          4        3112836 1451    3
 0.000000+0 0.000000+0          0          0         18          22836 1451    4
 77-Ir-171 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2836 1451    5
                      DIST-NOV07                       261107     2836 1451    6
----JEFF-311          MATERIAL 2836                               2836 1451    7
-----RADIOACTIVE DECAY DATA                                       2836 1451    8
------ENDF-6 FORMAT                                               2836 1451    9
******************************************************************2836 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2836 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2836 1451   12
**             Original data taken from:  NUBASE                **2836 1451   13
******************************************************************2836 1451   14
******************************************************************2836 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2836 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2836 1451   17
                                                                  2836 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2836 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2836 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2836 1451   21
******************************************************************2836 1451   22
                                1        451         24          02836 1451   23
                                8        457          5          02836 1451   24
 0.000000+0 0.000000+0          0          0          0          02836 1  099999
                                                                  2836 0  0    0
 7.71710+04 1.69503+02          0          0          0          02836 8457    1
 3.60000+00 1.00000+00          0          0          6          02836 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 5.85510+06 0.00000+002836 8457    3
 5.00000-01 1.00000+00          0          0          6          12836 8457    4
 4.00000+00 1.00000+00 5.85510+06 0.00000+00 1.00000+00 0.00000+002836 8457    5
                                                                  2836 8  099999
                                                                  2836 0  0    0
                                                                     0 0  0    0
 7.717100+4 1.695030+2         -1          0          2          12837 1451    1
 1.800000+5 1.000000+0          1          1          0          62837 1451    2
 0.000000+0 0.000000+0          0          0          4        3112837 1451    3
 0.000000+0 0.000000+0          0          0         18          22837 1451    4
 77-Ir-171MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2837 1451    5
                      DIST-NOV07                       261107     2837 1451    6
----JEFF-311          MATERIAL 2837                               2837 1451    7
-----RADIOACTIVE DECAY DATA                                       2837 1451    8
------ENDF-6 FORMAT                                               2837 1451    9
******************************************************************2837 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2837 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2837 1451   12
**             Original data taken from:  NUBASE                **2837 1451   13
******************************************************************2837 1451   14
******************************************************************2837 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2837 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2837 1451   17
                                                                  2837 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2837 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2837 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2837 1451   21
******************************************************************2837 1451   22
                                1        451         24          02837 1451   23
                                8        457          7          02837 1451   24
 0.000000+0 0.000000+0          0          0          0          02837 1  099999
                                                                  2837 0  0    0
 7.71710+04 1.69503+02          1          1          0          02837 8457    1
 1.40000+00 1.00000-01          0          0          6          02837 8457    2
 5.63010+05 0.00000+00 5.63010+05 0.00000+00 3.65745+06 0.00000+002837 8457    3
 5.50000+00-1.00000+00          0          0         18          32837 8457    4
 4.00000+00 0.00000+00 6.16510+06 0.00000+00 5.80000-01 0.00000+002837 8457    5
 2.00000+00 0.00000+00 8.04300+06 0.00000+00 2.10000-01 0.00000+002837 8457    6
 7.00000+00 0.00000+00 3.89001+05 0.00000+00 2.10000-01 0.00000+002837 8457    7
                                                                  2837 8  099999
                                                                  2837 0  0    0
                                                                     0 0  0    0
 7.717200+4 1.704930+2         -1          0          2          12838 1451    1
 0.000000+0 1.000000+0          0          0          0          62838 1451    2
 0.000000+0 0.000000+0          0          0          4        3112838 1451    3
 0.000000+0 0.000000+0          0          0         18          22838 1451    4
 77-Ir-172 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2838 1451    5
                      DIST-NOV07                       261107     2838 1451    6
----JEFF-311          MATERIAL 2838                               2838 1451    7
-----RADIOACTIVE DECAY DATA                                       2838 1451    8
------ENDF-6 FORMAT                                               2838 1451    9
******************************************************************2838 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2838 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2838 1451   12
**             Original data taken from:  NUBASE                **2838 1451   13
******************************************************************2838 1451   14
******************************************************************2838 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2838 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2838 1451   17
                                                                  2838 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2838 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2838 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2838 1451   21
******************************************************************2838 1451   22
                                1        451         24          02838 1451   23
                                8        457          6          02838 1451   24
 0.000000+0 0.000000+0          0          0          0          02838 1  099999
                                                                  2838 0  0    0
 7.71720+04 1.70493+02          0          0          0          02838 8457    1
 4.40000+00 3.00000-01          0          0          6          02838 8457    2
 3.17455+06 0.00000+00 3.17455+06 0.00000+00 1.16902+05 0.00000+002838 8457    3
 3.00000+00 1.00000+00          0          0         12          22838 8457    4
 2.00000+00 0.00000+00 9.71800+06 0.00000+00 9.80000-01 0.00000+002838 8457    5
 4.00000+00 0.00000+00 5.84510+06 0.00000+00 2.00000-02 0.00000+002838 8457    6
                                                                  2838 8  099999
                                                                  2838 0  0    0
                                                                     0 0  0    0
 7.717200+4 1.704930+2         -1          0          2          12839 1451    1
 1.390000+5 1.000000+0          1          1          0          62839 1451    2
 0.000000+0 0.000000+0          0          0          4        3112839 1451    3
 0.000000+0 0.000000+0          0          0         18          22839 1451    4
 77-Ir-172MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2839 1451    5
                      DIST-NOV07                       261107     2839 1451    6
----JEFF-311          MATERIAL 2839                               2839 1451    7
-----RADIOACTIVE DECAY DATA                                       2839 1451    8
------ENDF-6 FORMAT                                               2839 1451    9
******************************************************************2839 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2839 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2839 1451   12
**             Original data taken from:  NUBASE                **2839 1451   13
******************************************************************2839 1451   14
******************************************************************2839 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2839 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2839 1451   17
                                                                  2839 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2839 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2839 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2839 1451   21
******************************************************************2839 1451   22
                                1        451         24          02839 1451   23
                                8        457          6          02839 1451   24
 0.000000+0 0.000000+0          0          0          0          02839 1  099999
                                                                  2839 0  0    0
 7.71720+04 1.70493+02          1          1          0          02839 8457    1
 2.00000+00 1.00000-01          0          0          6          02839 8457    2
 2.52996+06 0.00000+00 2.52996+06 0.00000+00 1.37634+06 0.00000+002839 8457    3
 7.00000+00 1.00000+00          0          0         12          22839 8457    4
 2.00000+00 0.00000+00 9.85700+06 0.00000+00 7.70000-01 0.00000+002839 8457    5
 4.00000+00 0.00000+00 5.98410+06 0.00000+00 2.30000-01 0.00000+002839 8457    6
                                                                  2839 8  099999
                                                                  2839 0  0    0
                                                                     0 0  0    0
 7.717300+4 1.714820+2         -1          0          2          12840 1451    1
 0.000000+0 1.000000+0          0          0          0          62840 1451    2
 0.000000+0 0.000000+0          0          0          4        3112840 1451    3
 0.000000+0 0.000000+0          0          0         18          22840 1451    4
 77-Ir-173 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2840 1451    5
                      DIST-NOV07                       261107     2840 1451    6
----JEFF-311          MATERIAL 2840                               2840 1451    7
-----RADIOACTIVE DECAY DATA                                       2840 1451    8
------ENDF-6 FORMAT                                               2840 1451    9
******************************************************************2840 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2840 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2840 1451   12
**             Original data taken from:  NUBASE                **2840 1451   13
******************************************************************2840 1451   14
******************************************************************2840 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2840 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2840 1451   17
                                                                  2840 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2840 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2840 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2840 1451   21
******************************************************************2840 1451   22
                                1        451         24          02840 1451   23
                                8        457          7          02840 1451   24
 0.000000+0 0.000000+0          0          0          0          02840 1  099999
                                                                  2840 0  0    0
 7.71730+04 1.71482+02          0          0          0          02840 8457    1
 9.00000+00 8.00000-01          0          0          6          02840 8457    2
 2.22146+06 0.00000+00 2.22146+06 0.00000+00 3.92637+05 0.00000+002840 8457    3
-7.77770+01 0.00000+00          0          0         18          32840 8457    4
 2.00000+00 0.00000+00 7.16600+06 0.00000+00 9.30000-01 0.00000+002840 8457    5
 4.00000+00 0.00000+00 5.68910+06 0.00000+00 3.50000-02 0.00000+002840 8457    6
 4.00000+00 1.00000+00 5.52910+06 0.00000+00 3.50000-02 0.00000+002840 8457    7
                                                                  2840 8  099999
                                                                  2840 0  0    0
                                                                     0 0  0    0
 7.717300+4 1.714820+2         -1          0          2          12841 1451    1
 2.500000+5 1.000000+0          1          1          0          62841 1451    2
 0.000000+0 0.000000+0          0          0          4        3112841 1451    3
 0.000000+0 0.000000+0          0          0         18          22841 1451    4
 77-Ir-173MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2841 1451    5
                      DIST-NOV07                       261107     2841 1451    6
----JEFF-311          MATERIAL 2841                               2841 1451    7
-----RADIOACTIVE DECAY DATA                                       2841 1451    8
------ENDF-6 FORMAT                                               2841 1451    9
******************************************************************2841 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2841 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2841 1451   12
**             Original data taken from:  NUBASE                **2841 1451   13
******************************************************************2841 1451   14
******************************************************************2841 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2841 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2841 1451   17
                                                                  2841 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2841 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2841 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2841 1451   21
******************************************************************2841 1451   22
                                1        451         24          02841 1451   23
                                8        457          6          02841 1451   24
 0.000000+0 0.000000+0          0          0          0          02841 1  099999
                                                                  2841 0  0    0
 7.71730+04 1.71482+02          1          1          0          02841 8457    1
 2.20000+00 5.00000-02          0          0          6          02841 8457    2
 2.17536+06 0.00000+00 2.17536+06 0.00000+00 7.12692+05 0.00000+002841 8457    3
 5.50000+00-1.00000+00          0          0         12          22841 8457    4
 2.00000+00 0.00000+00 7.41600+06 0.00000+00 8.80000-01 0.00000+002841 8457    5
 4.00000+00 0.00000+00 5.93910+06 0.00000+00 1.20000-01 0.00000+002841 8457    6
                                                                  2841 8  099999
                                                                  2841 0  0    0
                                                                     0 0  0    0
 7.717400+4 1.724720+2         -1          0          2          12842 1451    1
 0.000000+0 1.000000+0          0          0          0          62842 1451    2
 0.000000+0 0.000000+0          0          0          4        3112842 1451    3
 0.000000+0 0.000000+0          0          0         18          22842 1451    4
 77-Ir-174 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2842 1451    5
                      DIST-NOV07                       261107     2842 1451    6
----JEFF-311          MATERIAL 2842                               2842 1451    7
-----RADIOACTIVE DECAY DATA                                       2842 1451    8
------ENDF-6 FORMAT                                               2842 1451    9
******************************************************************2842 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2842 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2842 1451   12
**             Original data taken from:  NUBASE                **2842 1451   13
******************************************************************2842 1451   14
******************************************************************2842 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2842 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2842 1451   17
                                                                  2842 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2842 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2842 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2842 1451   21
******************************************************************2842 1451   22
                                1        451         24          02842 1451   23
                                8        457          6          02842 1451   24
 0.000000+0 0.000000+0          0          0          0          02842 1  099999
                                                                  2842 0  0    0
 7.71740+04 1.72472+02          0          0          0          02842 8457    1
 7.90000+00 6.00000-01          0          0          6          02842 8457    2
 3.02712+06 0.00000+00 3.02712+06 0.00000+00 2.81205+04 0.00000+002842 8457    3
 3.00000+00 1.00000+00          0          0         12          22842 8457    4
 2.00000+00 0.00000+00 9.12700+06 0.00000+00 9.95000-01 0.00000+002842 8457    5
 4.00000+00 0.00000+00 5.62410+06 0.00000+00 5.00000-03 0.00000+002842 8457    6
                                                                  2842 8  099999
                                                                  2842 0  0    0
                                                                     0 0  0    0
 7.717400+4 1.724720+2         -1          0          2          12843 1451    1
 1.930000+5 1.000000+0          1          1          0          62843 1451    2
 0.000000+0 0.000000+0          0          0          4        3112843 1451    3
 0.000000+0 0.000000+0          0          0         18          22843 1451    4
 77-Ir-174MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2843 1451    5
                      DIST-NOV07                       261107     2843 1451    6
----JEFF-311          MATERIAL 2843                               2843 1451    7
-----RADIOACTIVE DECAY DATA                                       2843 1451    8
------ENDF-6 FORMAT                                               2843 1451    9
******************************************************************2843 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2843 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2843 1451   12
**             Original data taken from:  NUBASE                **2843 1451   13
******************************************************************2843 1451   14
******************************************************************2843 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2843 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2843 1451   17
                                                                  2843 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2843 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2843 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2843 1451   21
******************************************************************2843 1451   22
                                1        451         24          02843 1451   23
                                8        457          6          02843 1451   24
 0.000000+0 0.000000+0          0          0          0          02843 1  099999
                                                                  2843 0  0    0
 7.71740+04 1.72472+02          1          1          0          02843 8457    1
 4.90000+00 3.00000-01          0          0          6          02843 8457    2
 3.02900+06 0.00000+00 3.02900+06 0.00000+00 1.45428+05 0.00000+002843 8457    3
 7.00000+00 1.00000+00          0          0         12          22843 8457    4
 2.00000+00 0.00000+00 9.32000+06 0.00000+00 9.75000-01 0.00000+002843 8457    5
 4.00000+00 0.00000+00 5.81710+06 0.00000+00 2.50000-02 0.00000+002843 8457    6
                                                                  2843 8  099999
                                                                  2843 0  0    0
                                                                     0 0  0    0
 7.717500+4 1.734610+2         -1          0          2          12844 1451    1
 0.000000+0 1.000000+0          0          0          0          62844 1451    2
 0.000000+0 0.000000+0          0          0          4        3112844 1451    3
 0.000000+0 0.000000+0          0          0         18          22844 1451    4
 77-Ir-175 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2844 1451    5
                      DIST-NOV07                       261107     2844 1451    6
----JEFF-311          MATERIAL 2844                               2844 1451    7
-----RADIOACTIVE DECAY DATA                                       2844 1451    8
------ENDF-6 FORMAT                                               2844 1451    9
******************************************************************2844 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2844 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2844 1451   12
**             Original data taken from:  NUBASE                **2844 1451   13
******************************************************************2844 1451   14
******************************************************************2844 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2844 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2844 1451   17
                                                                  2844 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2844 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2844 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2844 1451   21
******************************************************************2844 1451   22
                                1        451         24          02844 1451   23
                                8        457          6          02844 1451   24
 0.000000+0 0.000000+0          0          0          0          02844 1  099999
                                                                  2844 0  0    0
 7.71750+04 1.73461+02          0          0          0          02844 8457    1
 9.00000+00 2.00000+00          0          0          6          02844 8457    2
 2.20642+06 0.00000+00 2.20642+06 0.00000+00 4.58669+04 0.00000+002844 8457    3
 2.50000+00-1.00000+00          0          0         12          22844 8457    4
 2.00000+00 0.00000+00 6.67600+06 0.00000+00 9.91500-01 0.00000+002844 8457    5
 4.00000+00 0.00000+00 5.39610+06 0.00000+00 8.50000-03 0.00000+002844 8457    6
                                                                  2844 8  099999
                                                                  2844 0  0    0
                                                                     0 0  0    0
 7.717600+4 1.744520+2         -1          0          2          12845 1451    1
 0.000000+0 1.000000+0          0          0          0          62845 1451    2
 0.000000+0 0.000000+0          0          0          4        3112845 1451    3
 0.000000+0 0.000000+0          0          0         18          22845 1451    4
 77-Ir-176 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2845 1451    5
                      DIST-NOV07                       261107     2845 1451    6
----JEFF-311          MATERIAL 2845                               2845 1451    7
-----RADIOACTIVE DECAY DATA                                       2845 1451    8
------ENDF-6 FORMAT                                               2845 1451    9
******************************************************************2845 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2845 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2845 1451   12
**             Original data taken from:  NUBASE                **2845 1451   13
******************************************************************2845 1451   14
******************************************************************2845 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2845 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2845 1451   17
                                                                  2845 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2845 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2845 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2845 1451   21
******************************************************************2845 1451   22
                                1        451         24          02845 1451   23
                                8        457          7          02845 1451   24
 0.000000+0 0.000000+0          0          0          0          02845 1  099999
                                                                  2845 0  0    0
 7.71760+04 1.74452+02          0          0          0          02845 8457    1
 8.30000+00 6.00000-01          0          0          6          02845 8457    2
 2.66055+06 0.00000+00 2.66055+06 0.00000+00 1.62257+05 0.00000+002845 8457    3
-7.77770+01 0.00000+00          0          0         18          32845 8457    4
 2.00000+00 0.00000+00 8.23700+06 0.00000+00 9.69000-01 0.00000+002845 8457    5
 4.00000+00 0.00000+00 5.23410+06 0.00000+00 1.55000-02 0.00000+002845 8457    6
 4.00000+00 1.00000+00 5.23410+06 0.00000+00 1.55000-02 0.00000+002845 8457    7
                                                                  2845 8  099999
                                                                  2845 0  0    0
                                                                     0 0  0    0
 7.717700+4 1.754410+2         -1          0          2          12846 1451    1
 0.000000+0 1.000000+0          0          0          0          62846 1451    2
 0.000000+0 0.000000+0          0          0          4        3112846 1451    3
 0.000000+0 0.000000+0          0          0         18          22846 1451    4
 77-Ir-177 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2846 1451    5
                      DIST-NOV07                       261107     2846 1451    6
----JEFF-311          MATERIAL 2846                               2846 1451    7
-----RADIOACTIVE DECAY DATA                                       2846 1451    8
------ENDF-6 FORMAT                                               2846 1451    9
******************************************************************2846 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2846 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2846 1451   12
**             Original data taken from:  NUBASE                **2846 1451   13
******************************************************************2846 1451   14
******************************************************************2846 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2846 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2846 1451   17
                                                                  2846 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2846 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2846 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2846 1451   21
******************************************************************2846 1451   22
                                1        451         24          02846 1451   23
                                8        457          6          02846 1451   24
 0.000000+0 0.000000+0          0          0          0          02846 1  099999
                                                                  2846 0  0    0
 7.71770+04 1.75441+02          0          0          0          02846 8457    1
 3.00000+01 2.00000+00          0          0          6          02846 8457    2
 1.96649+06 0.00000+00 1.96649+06 0.00000+00 3.04926+03 0.00000+002846 8457    3
 2.50000+00-1.00000+00          0          0         12          22846 8457    4
 2.00000+00 0.00000+00 5.90300+06 0.00000+00 9.99400-01 0.00000+002846 8457    5
 4.00000+00 0.00000+00 5.08210+06 0.00000+00 6.00000-04 0.00000+002846 8457    6
                                                                  2846 8  099999
                                                                  2846 0  0    0
                                                                     0 0  0    0
 7.717800+4 1.764320+2         -1          0          2          12847 1451    1
 0.000000+0 1.000000+0          0          0          0          62847 1451    2
 0.000000+0 0.000000+0          0          0          4        3112847 1451    3
 0.000000+0 0.000000+0          0          0         18          22847 1451    4
 77-Ir-178 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2847 1451    5
                      DIST-NOV07                       261107     2847 1451    6
----JEFF-311          MATERIAL 2847                               2847 1451    7
-----RADIOACTIVE DECAY DATA                                       2847 1451    8
------ENDF-6 FORMAT                                               2847 1451    9
******************************************************************2847 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2847 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2847 1451   12
**             Original data taken from:  NUBASE                **2847 1451   13
******************************************************************2847 1451   14
******************************************************************2847 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2847 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2847 1451   17
                                                                  2847 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2847 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2847 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2847 1451   21
******************************************************************2847 1451   22
                                1        451         24          02847 1451   23
                                8        457          5          02847 1451   24
 0.000000+0 0.000000+0          0          0          0          02847 1  099999
                                                                  2847 0  0    0
 7.71780+04 1.76432+02          0          0          0          02847 8457    1
 1.20000+01 2.00000+00          0          0          6          02847 8457    2
 2.43133+06 0.00000+00 2.43133+06 0.00000+00 0.00000+00 0.00000+002847 8457    3
-7.77770+01 0.00000+00          0          0          6          12847 8457    4
 2.00000+00 0.00000+00 7.29400+06 0.00000+00 1.00000+00 0.00000+002847 8457    5
                                                                  2847 8  099999
                                                                  2847 0  0    0
                                                                     0 0  0    0
 7.717900+4 1.774220+2         -1          0          2          12848 1451    1
 0.000000+0 1.000000+0          0          0          0          62848 1451    2
 0.000000+0 0.000000+0          0          0          4        3112848 1451    3
 0.000000+0 0.000000+0          0          0         18          22848 1451    4
 77-Ir-179 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2848 1451    5
                      DIST-NOV07                       261107     2848 1451    6
----JEFF-311          MATERIAL 2848                               2848 1451    7
-----RADIOACTIVE DECAY DATA                                       2848 1451    8
------ENDF-6 FORMAT                                               2848 1451    9
******************************************************************2848 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2848 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2848 1451   12
**             Original data taken from:  NUBASE                **2848 1451   13
******************************************************************2848 1451   14
******************************************************************2848 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2848 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2848 1451   17
                                                                  2848 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2848 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2848 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2848 1451   21
******************************************************************2848 1451   22
                                1        451         24          02848 1451   23
                                8        457          5          02848 1451   24
 0.000000+0 0.000000+0          0          0          0          02848 1  099999
                                                                  2848 0  0    0
 7.71790+04 1.77422+02          0          0          0          02848 8457    1
 7.90000+01 1.00000+00          0          0          6          02848 8457    2
 1.64767+06 0.00000+00 1.64767+06 0.00000+00 0.00000+00 0.00000+002848 8457    3
 2.50000+00-1.00000+00          0          0          6          12848 8457    4
 2.00000+00 0.00000+00 4.94300+06 0.00000+00 1.00000+00 0.00000+002848 8457    5
                                                                  2848 8  099999
                                                                  2848 0  0    0
                                                                     0 0  0    0
 7.718000+4 1.784130+2         -1          0          2          12849 1451    1
 0.000000+0 1.000000+0          0          0          0          62849 1451    2
 0.000000+0 0.000000+0          0          0          4        3112849 1451    3
 0.000000+0 0.000000+0          0          0         18          22849 1451    4
 77-Ir-180 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2849 1451    5
                      DIST-NOV07                       261107     2849 1451    6
----JEFF-311          MATERIAL 2849                               2849 1451    7
-----RADIOACTIVE DECAY DATA                                       2849 1451    8
------ENDF-6 FORMAT                                               2849 1451    9
******************************************************************2849 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2849 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2849 1451   12
**             Original data taken from:  NUBASE                **2849 1451   13
******************************************************************2849 1451   14
******************************************************************2849 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2849 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2849 1451   17
                                                                  2849 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2849 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2849 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2849 1451   21
******************************************************************2849 1451   22
                                1        451         24          02849 1451   23
                                8        457          5          02849 1451   24
 0.000000+0 0.000000+0          0          0          0          02849 1  099999
                                                                  2849 0  0    0
 7.71800+04 1.78413+02          0          0          0          02849 8457    1
 9.00000+01 6.00000+00          0          0          6          02849 8457    2
 2.12700+06 0.00000+00 2.12700+06 0.00000+00 0.00000+00 0.00000+002849 8457    3
-7.77770+01 0.00000+00          0          0          6          12849 8457    4
 2.00000+00 0.00000+00 6.38100+06 0.00000+00 1.00000+00 0.00000+002849 8457    5
                                                                  2849 8  099999
                                                                  2849 0  0    0
                                                                     0 0  0    0
 7.718100+4 1.794030+2         -1          0          2          12850 1451    1
 0.000000+0 1.000000+0          0          0          0          62850 1451    2
 0.000000+0 0.000000+0          0          0          4        3112850 1451    3
 0.000000+0 0.000000+0          0          0         18          22850 1451    4
 77-Ir-181 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2850 1451    5
                      DIST-NOV07                       261107     2850 1451    6
----JEFF-311          MATERIAL 2850                               2850 1451    7
-----RADIOACTIVE DECAY DATA                                       2850 1451    8
------ENDF-6 FORMAT                                               2850 1451    9
******************************************************************2850 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2850 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2850 1451   12
**             Original data taken from:  NUBASE                **2850 1451   13
******************************************************************2850 1451   14
******************************************************************2850 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2850 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2850 1451   17
                                                                  2850 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2850 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2850 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2850 1451   21
******************************************************************2850 1451   22
                                1        451         24          02850 1451   23
                                8        457          6          02850 1451   24
 0.000000+0 0.000000+0          0          0          0          02850 1  099999
                                                                  2850 0  0    0
 7.71810+04 1.79403+02          0          0          0          02850 8457    1
 2.94000+02 9.00000+00          0          0          6          02850 8457    2
 1.35118+06 0.00000+00 1.35118+06 0.00000+00 0.00000+00 0.00000+002850 8457    3
 2.50000+00-1.00000+00          0          0         12          22850 8457    4
 2.00000+00 0.00000+00 4.07800+06 0.00000+00 5.00000-01 0.00000+002850 8457    5
 2.00000+00 1.00000+00 4.02910+06 0.00000+00 5.00000-01 0.00000+002850 8457    6
                                                                  2850 8  099999
                                                                  2850 0  0    0
                                                                     0 0  0    0
 7.718200+4 1.803950+2         -1          0          2          12851 1451    1
 0.000000+0 1.000000+0          0          0          0          62851 1451    2
 0.000000+0 0.000000+0          0          0          4        3112851 1451    3
 0.000000+0 0.000000+0          0          0         18          22851 1451    4
 77-Ir-182 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2851 1451    5
                      DIST-NOV07                       261107     2851 1451    6
----JEFF-311          MATERIAL 2851                               2851 1451    7
-----RADIOACTIVE DECAY DATA                                       2851 1451    8
------ENDF-6 FORMAT                                               2851 1451    9
******************************************************************2851 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2851 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2851 1451   12
**             Original data taken from:  NUBASE                **2851 1451   13
******************************************************************2851 1451   14
******************************************************************2851 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2851 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2851 1451   17
                                                                  2851 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2851 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2851 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2851 1451   21
******************************************************************2851 1451   22
                                1        451         24          02851 1451   23
                                8        457          5          02851 1451   24
 0.000000+0 0.000000+0          0          0          0          02851 1  099999
                                                                  2851 0  0    0
 7.71820+04 1.80395+02          0          0          0          02851 8457    1
 9.00000+02 6.00000+01          0          0          6          02851 8457    2
 1.85233+06 0.00000+00 1.85233+06 0.00000+00 0.00000+00 0.00000+002851 8457    3
 3.00000+00 1.00000+00          0          0          6          12851 8457    4
 2.00000+00 0.00000+00 5.55700+06 0.00000+00 1.00000+00 0.00000+002851 8457    5
                                                                  2851 8  099999
                                                                  2851 0  0    0
                                                                     0 0  0    0
 7.718300+4 1.813850+2         -1          0          2          12852 1451    1
 0.000000+0 1.000000+0          0          0          0          62852 1451    2
 0.000000+0 0.000000+0          0          0          4        3112852 1451    3
 0.000000+0 0.000000+0          0          0         18          22852 1451    4
 77-Ir-183 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2852 1451    5
                      DIST-NOV07                       261107     2852 1451    6
----JEFF-311          MATERIAL 2852                               2852 1451    7
-----RADIOACTIVE DECAY DATA                                       2852 1451    8
------ENDF-6 FORMAT                                               2852 1451    9
******************************************************************2852 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2852 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2852 1451   12
**             Original data taken from:  NUBASE                **2852 1451   13
******************************************************************2852 1451   14
******************************************************************2852 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2852 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2852 1451   17
                                                                  2852 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2852 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2852 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2852 1451   21
******************************************************************2852 1451   22
                                1        451         24          02852 1451   23
                                8        457          7          02852 1451   24
 0.000000+0 0.000000+0          0          0          0          02852 1  099999
                                                                  2852 0  0    0
 7.71830+04 1.81385+02          0          0          0          02852 8457    1
 3.48000+03 3.00000+02          0          0          6          02852 8457    2
 1.11565+06 0.00000+00 1.11565+06 0.00000+00 1.98205+03 0.00000+002852 8457    3
 2.50000+00-1.00000+00          0          0         18          32852 8457    4
 2.00000+00 0.00000+00 3.46300+06 0.00000+00 3.29835-01 0.00000+002852 8457    5
 2.00000+00 1.00000+00 3.29229+06 0.00000+00 6.69665-01 0.00000+002852 8457    6
 4.00000+00 0.00000+00 3.96410+06 0.00000+00 5.00000-04 0.00000+002852 8457    7
                                                                  2852 8  099999
                                                                  2852 0  0    0
                                                                     0 0  0    0
 7.718400+4 1.823770+2         -1          0          2          12853 1451    1
 0.000000+0 1.000000+0          0          0          0          62853 1451    2
 0.000000+0 0.000000+0          0          0          4        3112853 1451    3
 0.000000+0 0.000000+0          0          0         18          22853 1451    4
 77-Ir-184 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2853 1451    5
                      DIST-NOV07                       261107     2853 1451    6
----JEFF-311          MATERIAL 2853                               2853 1451    7
-----RADIOACTIVE DECAY DATA                                       2853 1451    8
------ENDF-6 FORMAT                                               2853 1451    9
******************************************************************2853 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2853 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2853 1451   12
**             Original data taken from:  NUBASE                **2853 1451   13
******************************************************************2853 1451   14
******************************************************************2853 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2853 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2853 1451   17
                                                                  2853 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2853 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2853 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2853 1451   21
******************************************************************2853 1451   22
                                1        451         24          02853 1451   23
                                8        457          5          02853 1451   24
 0.000000+0 0.000000+0          0          0          0          02853 1  099999
                                                                  2853 0  0    0
 7.71840+04 1.82377+02          0          0          0          02853 8457    1
 1.11240+04 1.08000+02          0          0          6          02853 8457    2
 1.54837+06 0.00000+00 1.54837+06 0.00000+00 0.00000+00 0.00000+002853 8457    3
 5.00000+00-1.00000+00          0          0          6          12853 8457    4
 2.00000+00 0.00000+00 4.64510+06 0.00000+00 1.00000+00 0.00000+002853 8457    5
                                                                  2853 8  099999
                                                                  2853 0  0    0
                                                                     0 0  0    0
 7.718500+4 1.833680+2         -1          0          2          12854 1451    1
 0.000000+0 1.000000+0          0          0          0          62854 1451    2
 0.000000+0 0.000000+0          0          0          4        3112854 1451    3
 0.000000+0 0.000000+0          0          0         18          22854 1451    4
 77-Ir-185 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2854 1451    5
                      DIST-NOV07                       261107     2854 1451    6
----JEFF-311          MATERIAL 2854                               2854 1451    7
-----RADIOACTIVE DECAY DATA                                       2854 1451    8
------ENDF-6 FORMAT                                               2854 1451    9
******************************************************************2854 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2854 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2854 1451   12
**             Original data taken from:  NUBASE                **2854 1451   13
******************************************************************2854 1451   14
******************************************************************2854 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2854 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2854 1451   17
                                                                  2854 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2854 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2854 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2854 1451   21
******************************************************************2854 1451   22
                                1        451         24          02854 1451   23
                                8        457          5          02854 1451   24
 0.000000+0 0.000000+0          0          0          0          02854 1  099999
                                                                  2854 0  0    0
 7.71850+04 1.83368+02          0          0          0          02854 8457    1
 5.18400+04 3.60000+02          0          0          6          02854 8457    2
 8.24465+05 0.00000+00 8.24465+05 0.00000+00 0.00000+00 0.00000+002854 8457    3
 2.50000+00-1.00000+00          0          0          6          12854 8457    4
 2.00000+00 0.00000+00 2.47340+06 0.00000+00 1.00000+00 0.00000+002854 8457    5
                                                                  2854 8  099999
                                                                  2854 0  0    0
                                                                     0 0  0    0
 7.718600+4 1.843600+2         -1          0          2          12855 1451    1
 0.000000+0 1.000000+0          0          0          0          62855 1451    2
 0.000000+0 0.000000+0          0          0          4        3112855 1451    3
 0.000000+0 0.000000+0          0          0         18          22855 1451    4
 77-Ir-186 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2855 1451    5
                      DIST-NOV07                       261107     2855 1451    6
----JEFF-311          MATERIAL 2855                               2855 1451    7
-----RADIOACTIVE DECAY DATA                                       2855 1451    8
------ENDF-6 FORMAT                                               2855 1451    9
******************************************************************2855 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2855 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2855 1451   12
**             Original data taken from:  NUBASE                **2855 1451   13
******************************************************************2855 1451   14
******************************************************************2855 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2855 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2855 1451   17
                                                                  2855 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2855 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2855 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2855 1451   21
******************************************************************2855 1451   22
                                1        451         24          02855 1451   23
                                8        457          5          02855 1451   24
 0.000000+0 0.000000+0          0          0          0          02855 1  099999
                                                                  2855 0  0    0
 7.71860+04 1.84360+02          0          0          0          02855 8457    1
 5.99040+04 1.08000+02          0          0          6          02855 8457    2
 1.27550+06 0.00000+00 1.27550+06 0.00000+00 0.00000+00 0.00000+002855 8457    3
 5.00000+00 1.00000+00          0          0          6          12855 8457    4
 2.00000+00 0.00000+00 3.82650+06 0.00000+00 1.00000+00 0.00000+002855 8457    5
                                                                  2855 8  099999
                                                                  2855 0  0    0
                                                                     0 0  0    0
 7.718600+4 1.843600+2         -1          0          2          12856 1451    1
 8.000000+2 1.000000+0          1          1          0          62856 1451    2
 0.000000+0 0.000000+0          0          0          4        3112856 1451    3
 0.000000+0 0.000000+0          0          0         18          22856 1451    4
 77-Ir-186MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2856 1451    5
                      DIST-NOV07                       261107     2856 1451    6
----JEFF-311          MATERIAL 2856                               2856 1451    7
-----RADIOACTIVE DECAY DATA                                       2856 1451    8
------ENDF-6 FORMAT                                               2856 1451    9
******************************************************************2856 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2856 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2856 1451   12
**             Original data taken from:  NUBASE                **2856 1451   13
******************************************************************2856 1451   14
******************************************************************2856 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2856 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2856 1451   17
                                                                  2856 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2856 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2856 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2856 1451   21
******************************************************************2856 1451   22
                                1        451         24          02856 1451   23
                                8        457          6          02856 1451   24
 0.000000+0 0.000000+0          0          0          0          02856 1  099999
                                                                  2856 0  0    0
 7.71860+04 1.84360+02          1          1          0          02856 8457    1
 6.91200+03 1.80000+02          0          0          6          02856 8457    2
 9.56825+05 0.00000+00 9.57025+05 0.00000+00 0.00000+00 0.00000+002856 8457    3
 2.00000+00-1.00000+00          0          0         12          22856 8457    4
 2.00000+00 0.00000+00 3.82730+06 0.00000+00 7.50000-01 0.00000+002856 8457    5
 3.00000+00 0.00000+00 8.00000+02 0.00000+00 2.50000-01 0.00000+002856 8457    6
                                                                  2856 8  099999
                                                                  2856 0  0    0
                                                                     0 0  0    0
 7.718700+4 1.853510+2         -1          0          2          12857 1451    1
 0.000000+0 1.000000+0          0          0          0          62857 1451    2
 0.000000+0 0.000000+0          0          0          4        3112857 1451    3
 0.000000+0 0.000000+0          0          0        102          22857 1451    4
 77-Ir-187 HAR+WIN    EVAL-OCT00 A.L. NICHOLS                     2857 1451    5
                      DIST-NOV07                       261107     2857 1451    6
----JEFF-311          MATERIAL 2857                               2857 1451    7
-----RADIOACTIVE DECAY DATA                                       2857 1451    8
------ENDF-6 FORMAT                                               2857 1451    9
******************************************************************2857 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2857 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2857 1451   12
**             Original data taken from:  UKPADD67              **2857 1451   13
******************************************************************2857 1451   14
                                                                  2857 1451   15
          R B FIRESTONE              NUCL DATA SHEETS 62(1991)159 2857 1451   16
          R M DIAMOND, M J HOLLANDER NUCL PHYS 8(1958)143         2857 1451   17
          L N KRYUKOVA ET AL         BULL ACAD SCI USSR PHYS      2857 1451   18
                                     SER 25(1961)1269             2857 1451   19
          G T EMERY ET AL            PHYS REV 129(1963)2597       2857 1451   20
          S G MALMSKOG ET AL         NUCL PHYS A166(1971)573      2857 1451   21
          K AHLGREN, P J DALY        NUCL PHYS A189(1972)368      2857 1451   22
          V V BABENKO ET AL          PROC 24TH ANNUAL CONFERENCE  2857 1451   23
                                     NUCL SPECTROS STRUCTURE      2857 1451   24
                                     ATOMIC NUCLEI, BAKU (1976)1292857 1451   25
          N B GOVE, M J MARTIN       NUCL DATA TABLES 10(1971)20  2857 1451   26
                                                                  2857 1451   27
 A half-life of 10.5(3) hours has been adopted from the studies of2857 1451   28
Emery et al - further measurements are required to confirm the    2857 1451   29
merit of this value.                                              2857 1451   30
                                                                  2857 1451   31
 The reasonably complex decay scheme has been derived from the    2857 1451   32
relative gamma-ray emission probabilities measured by Malmskog et 2857 1451   33
al, Ahlgren and Daly, and Babenko et al (quoted in terms of the   2857 1451   34
912.95 keV gamma ray (100%)).  Adjustments were made to the       2857 1451   35
relative emission probabilities of the 156.7, 180.9, 266.2 and    2857 1451   36
384.9 keV gamma rays, and arbitrary assignments were made with    2857 1451   37
respect to the emission probabilities of the unresolved 323.2-    2857 1451   38
323.5, 400.9-401.0 and 654.0-654.4 keV transitions; these         2857 1451   39
manipulations were based on population/depopulation balances for  2857 1451   40
specific nuclear levels, and assumed zero EC transitions to the   2857 1451   41
556.9, 445.0, 333.26, 257.2, 190.60 and 100.55 keV nuclear levels 2857 1451   42
of Os-187 (from spin and parity considerations).  A significant   2857 1451   43
number of previously unplaced gamma-ray transitions have been     2857 1451   44
introduced into the decay scheme (163.0, 182.2, 198.5, 207,       2857 1451   45
211.6, 232.0, 277.7, 370.7, 376, 412.7, 422.5, 564.8, 742, 787.9, 2857 1451   46
814.0 and 1012.3 keV gamma rays), with the creation of eight      2857 1451   47
additional nuclear levels (1086.6, 1034.8, 933, 888.4, 874.2,     2857 1451   48
768.5, 755.4 and 422.5 keV).  There are large differences between 2857 1451   49
some of the measured relative emission probabilities that require 2857 1451   50
resolution (eg., 177.65, 187.40, 224.3, 253.0, 299.7, 376 keV and 2857 1451   51
others).  Furthermore, there is a lack of measurements of the     2857 1451   52
lower-energy gamma-ray emission probabilities that needs to be    2857 1451   53
addressed, particularly for 9.746, 25.5, 64.58, 65.29, 74.33,     2857 1451   54
75.04, 86.9 and 90.80 keV gamma rays.                             2857 1451   55
                                                                  2857 1451   56
 A large number of the gamma-ray transitions have M1+E2           2857 1451   57
multipolarity, and their theoretical internal conversion          2857 1451   58
coefficients were calculated from known mixing ratios, or         2857 1451   59
assuming values based on 100% M1 or 50%M1 + 50%E2.  The weighted- 2857 1451   60
mean relative emission probabilities and theoretical internal     2857 1451   61
conversion coefficients of the gamma-ray transitions were used to 2857 1451   62
calculate relative EC transition probabilities to the higher-     2857 1451   63
energy nuclear levels.  All EC transitions were assumed to be     2857 1451   64
first forbidden non-unique.  Major assumptions in the production  2857 1451   65
of a comprehensive decay scheme were that the absolute EC         2857 1451   66
transition probabilities to the 0-9.746 and 74.33-75.04 keV       2857 1451   67
nuclear levels are 0.26(3) and 0.34(3) respectively, with re-     2857 1451   68
assigned EC transition probabilities of 0.02 and 0.24 for the 0   2857 1451   69
and 9.746 keV nuclear levels respectively, and 0.12 and 0.22 for  2857 1451   70
the 74.33 and 75.04 keV nuclear levels respectively.  These key   2857 1451   71
data are only intuitive, and more reliable values are required.   2857 1451   72
                                                                  2857 1451   73
 A combination of weighted-mean gamma-ray emission probability    2857 1451   74
data and various arguable assumptions have been used to calculate 2857 1451   75
the decay scheme.  The Q(EC)-value was based on energy            2857 1451   76
systematics, and was subsequently used to derive the EC           2857 1451   77
transition energies.  Further detailed measurements are required  2857 1451   78
to resolve some of the more significant discrepancies in the      2857 1451   79
proposed decay scheme, particularly additional half-life studies, 2857 1451   80
and determination of the emission probabilities of the lower-     2857 1451   81
energy gamma-ray transitions (< 100 keV) and the absolute         2857 1451   82
emission probabilities of the gamma rays (ie., normalisation      2857 1451   83
factor).                                                          2857 1451   84
                                                                  2857 1451   85
                                                                  2857 1451   86
      MEAN BETA+ ENERGIES:-                                       2857 1451   87
   END POINT(MEV)= 0.4060  SHAPE= 1  MEAN= 0.2030  INT= 0.0000    2857 1451   88
   END POINT(MEV)= 0.4070  SHAPE= 1  MEAN= 0.2034  INT= 0.0000    2857 1451   89
   END POINT(MEV)= 0.4710  SHAPE= 1  MEAN= 0.2324  INT= 0.0000    2857 1451   90
   END POINT(MEV)= 0.4810  SHAPE= 1  MEAN= 0.2369  INT= 0.0000    2857 1451   91
                                                                  2857 1451   92
      MEAN GAMMA ENERGY              =    243.4445  KEV           2857 1451   93
      MAX. ANNIHILATION INTENSITY    =      0.0001                2857 1451   94
      MEAN BETA+ ENERGY              =      0.0117  KEV           2857 1451   95
      BETA+ + NEUTRINO ENERGY        =   1200.6467  KEV           2857 1451   96
      MEAN X-RAY ENERGY              =     57.7711  KEV           2857 1451   97
      MEAN AUGER ELECTRON ENERGY     =     14.2360  KEV           2857 1451   98
      MEAN CONVERSION ELECTRON ENERGY=     49.5414  KEV           2857 1451   99
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.2359  KEV           2857 1451  100
      EFFECTIVE Q VALUE              =   1503.0000  KEV           2857 1451  101
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.6653                2857 1451  102
      CALCULATED Q VALUE             =   1503.9326  KEV           2857 1451  103
      % DEVIATION                    =     -0.0621                2857 1451  104
                                                                  2857 1451  105
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2857 1451  106
                                1        451        108          12857 1451  107
                                8        457        909          12857 1451  108
 0.000000+0 0.000000+0          0          0          0          02857 1  099999
                                                                  2857 0  0    0
7.71870E+041.85351E+02          0          0          0          42857 8457    1
3.78000E+041.08000E+03          0          0          6          02857 8457    2
6.37891E+045.15462E+033.01506E+052.26734E+040.00000E+000.00000E+002857 8457    3
1.50000E+00 1.0000E+00          0          0          6          12857 8457    4
2.00000E+000.00000E+001.50300E+061.00000E+041.00000E+000.00000E+002857 8457    5
0.00000E+000.00000E+00          0          0          6         962857 8457    6
4.48000E-024.00000E-032.43445E+052.19250E+040.00000E+000.00000E+002857 8457    7
9.74600E+032.40000E+01          0          0         12          02857 8457    8
2.00000E+000.00000E+004.90000E-024.00000E-030.00000E+000.00000E+002857 8457    9
2.67000E+022.99040E+010.00000E+000.00000E+000.00000E+000.00000E+002857 8457   10
2.55000E+041.00000E+02          0          0         12          02857 8457   11
2.00000E+000.00000E+003.64000E-027.00000E-030.00000E+000.00000E+002857 8457   12
5.70000E+015.98500E+000.00000E+000.00000E+004.40000E+014.62000E+002857 8457   13
6.45800E+045.00000E+01          0          0         12          02857 8457   14
2.00000E+000.00000E+002.65000E-011.50000E-020.00000E+000.00000E+002857 8457   15
4.10000E+004.01800E-010.00000E+000.00000E+003.10000E+003.03800E-012857 8457   16
6.52900E+045.00000E+01          0          0         12          02857 8457   17
2.00000E+000.00000E+001.52000E-011.50000E-020.00000E+000.00000E+002857 8457   18
2.50000E+012.00000E+000.00000E+000.00000E+001.89000E+011.51200E+002857 8457   19
7.43300E+043.00000E+01          0          0         12          02857 8457   20
2.00000E+000.00000E+007.20000E-014.00000E-020.00000E+000.00000E+002857 8457   21
4.20000E+003.99000E-010.00000E+000.00000E+001.90000E+001.80500E-012857 8457   22
7.50400E+043.00000E+01          0          0         12          02857 8457   23
2.00000E+000.00000E+002.10000E-012.00000E-020.00000E+000.00000E+002857 8457   24
1.49000E+011.93700E-018.00000E-011.04000E-021.06000E+011.37800E-012857 8457   25
8.49000E+041.00000E+02          0          0         12          02857 8457   26
2.00000E+000.00000E+002.40000E-022.00000E-030.00000E+000.00000E+002857 8457   27
9.50000E+001.04500E-017.80000E+008.58000E-021.30000E+001.43000E-022857 8457   28
8.69000E+041.00000E+02          0          0         12          02857 8457   29
2.00000E+000.00000E+009.00000E-031.00000E-030.00000E+000.00000E+002857 8457   30
8.85000E+008.85000E-027.30000E+007.30000E-021.20000E+001.20000E-022857 8457   31
9.08000E+049.00000E+01          0          0         12          02857 8457   32
2.00000E+000.00000E+001.30000E-035.00000E-040.00000E+000.00000E+002857 8457   33
6.60000E+009.90000E-029.00000E-011.35000E-024.30000E+006.45000E-022857 8457   34
1.12400E+051.00000E+02          0          0         12          02857 8457   35
2.00000E+000.00000E+008.00000E-032.00000E-030.00000E+000.00000E+002857 8457   36
2.78000E+003.05800E-026.60000E-017.26000E-031.60000E+001.76000E-022857 8457   37
1.13100E+051.00000E+02          0          0         12          02857 8457   38
2.00000E+000.00000E+004.10000E-023.00000E-030.00000E+000.00000E+002857 8457   39
3.10000E+003.00700E-011.50000E+001.45500E-011.20000E+001.16400E-012857 8457   40
1.15600E+051.00000E+02          0          0         12          02857 8457   41
2.00000E+000.00000E+008.00000E-032.00000E-030.00000E+000.00000E+002857 8457   42
3.00000E+003.00000E-011.60000E+001.60000E-011.10000E+001.10000E-012857 8457   43
1.45900E+051.00000E+02          0          0         12          02857 8457   44
2.00000E+000.00000E+006.00000E-031.00000E-030.00000E+000.00000E+002857 8457   45
1.50000E+001.99500E-011.00000E+001.33000E-013.80000E-015.05400E-022857 8457   46
1.56700E+052.00000E+02          0          0         12          02857 8457   47
2.00000E+000.00000E+005.20000E-032.00000E-030.00000E+000.00000E+002857 8457   48
9.80000E+009.01600E-016.65000E+006.11800E-012.40000E+002.20800E-012857 8457   49
1.62700E+051.00000E+02          0          0         12          02857 8457   50
2.00000E+000.00000E+002.50000E-024.00000E-030.00000E+000.00000E+002857 8457   51
1.47000E+002.05800E-021.22000E+001.70800E-022.00000E-012.80000E-032857 8457   52
1.63000E+056.00000E+02          0          0         12          02857 8457   53
2.00000E+000.00000E+001.50000E-022.00000E-030.00000E+000.00000E+002857 8457   54
1.46000E+002.04400E-021.21000E+001.69400E-022.00000E-012.80000E-032857 8457   55
1.77650E+056.00000E+01          0          0         12          02857 8457   56
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2.00000E+000.00000E+004.97280E-054.97280E-060.00000E+000.00000E+002857 8457  751
6.51942E+053.25971E+04          0          0          6          02857 8457  752
2.00000E+000.00000E+002.94336E-062.94336E-070.00000E+000.00000E+002857 8457  753
6.53259E+053.26630E+04          0          0          6          02857 8457  754
2.00000E+000.00000E+003.74976E-063.74976E-070.00000E+000.00000E+002857 8457  755
6.61672E+053.30836E+04          0          0          6          02857 8457  756
2.00000E+000.00000E+001.08864E-061.08864E-070.00000E+000.00000E+002857 8457  757
6.73729E+053.36865E+04          0          0          6          02857 8457  758
2.00000E+000.00000E+003.27398E-053.27398E-060.00000E+000.00000E+002857 8457  759
6.83229E+053.41615E+04          0          0          6          02857 8457  760
2.00000E+000.00000E+003.74438E-053.74438E-060.00000E+000.00000E+002857 8457  761
6.90629E+053.45315E+04          0          0          6          02857 8457  762
2.00000E+000.00000E+001.45152E-061.45152E-070.00000E+000.00000E+002857 8457  763
6.99042E+053.49521E+04          0          0          6          02857 8457  764
2.00000E+000.00000E+004.30080E-074.30080E-080.00000E+000.00000E+002857 8457  765
7.00329E+053.50165E+04          0          0          6          02857 8457  766
2.00000E+000.00000E+001.36192E-061.36192E-070.00000E+000.00000E+002857 8457  767
7.05129E+053.52565E+04          0          0          6          02857 8457  768
2.00000E+000.00000E+005.94048E-065.94048E-070.00000E+000.00000E+002857 8457  769
7.08742E+053.54371E+04          0          0          6          02857 8457  770
2.00000E+000.00000E+004.25600E-074.25600E-080.00000E+000.00000E+002857 8457  771
7.13542E+053.56771E+04          0          0          6          02857 8457  772
2.00000E+000.00000E+001.82784E-061.82784E-070.00000E+000.00000E+002857 8457  773
7.14869E+053.57435E+04          0          0          6          02857 8457  774
2.00000E+000.00000E+008.96000E-068.96000E-070.00000E+000.00000E+002857 8457  775
7.22829E+053.61415E+04          0          0          6          02857 8457  776
2.00000E+000.00000E+008.60160E-078.60160E-080.00000E+000.00000E+002857 8457  777
7.23282E+053.61641E+04          0          0          6          02857 8457  778
2.00000E+000.00000E+002.68800E-062.68800E-070.00000E+000.00000E+002857 8457  779
7.26029E+053.63015E+04          0          0          6          02857 8457  780
2.00000E+000.00000E+001.44932E-041.44932E-050.00000E+000.00000E+002857 8457  781
7.36729E+053.68365E+04          0          0          6          02857 8457  782
2.00000E+000.00000E+005.45664E-065.45664E-070.00000E+000.00000E+002857 8457  783
7.45142E+053.72571E+04          0          0          6          02857 8457  784
2.00000E+000.00000E+001.81888E-061.81888E-070.00000E+000.00000E+002857 8457  785
7.46229E+053.73115E+04          0          0          6          02857 8457  786
2.00000E+000.00000E+005.83296E-065.83296E-070.00000E+000.00000E+002857 8457  787
7.54642E+053.77321E+04          0          0          6          02857 8457  788
2.00000E+000.00000E+001.69344E-061.69344E-070.00000E+000.00000E+002857 8457  789
7.67429E+053.83715E+04          0          0          6          02857 8457  790
2.00000E+000.00000E+002.77536E-052.77536E-060.00000E+000.00000E+002857 8457  791
7.85829E+053.92915E+04          0          0          6          02857 8457  792
2.00000E+000.00000E+001.61280E-071.61280E-080.00000E+000.00000E+002857 8457  793
7.86829E+053.93415E+04          0          0          6          02857 8457  794
2.00000E+000.00000E+007.98336E-067.98336E-070.00000E+000.00000E+002857 8457  795
7.89029E+053.94515E+04          0          0          6          02857 8457  796
2.00000E+000.00000E+002.26195E-052.26195E-060.00000E+000.00000E+002857 8457  797
7.94242E+053.97121E+04          0          0          6          02857 8457  798
2.00000E+000.00000E+005.37600E-085.37600E-090.00000E+000.00000E+002857 8457  799
7.97442E+053.98721E+04          0          0          6          02857 8457  800
2.00000E+000.00000E+006.70208E-066.70208E-070.00000E+000.00000E+002857 8457  801
8.12829E+054.06415E+04          0          0          6          02857 8457  802
2.00000E+000.00000E+006.25363E-066.25363E-070.00000E+000.00000E+002857 8457  803
8.25929E+054.12965E+04          0          0          6          02857 8457  804
2.00000E+000.00000E+009.22208E-069.22208E-070.00000E+000.00000E+002857 8457  805
8.29129E+054.14565E+04          0          0          6          02857 8457  806
2.00000E+000.00000E+003.49798E-053.49798E-060.00000E+000.00000E+002857 8457  807
8.30429E+054.15215E+04          0          0          6          02857 8457  808
2.00000E+000.00000E+004.49344E-064.49344E-070.00000E+000.00000E+002857 8457  809
8.38842E+054.19421E+04          0          0          6          02857 8457  810
2.00000E+000.00000E+001.32160E-061.32160E-070.00000E+000.00000E+002857 8457  811
8.39079E+054.19540E+04          0          0          6          02857 8457  812
2.00000E+000.00000E+005.55520E-045.55520E-050.00000E+000.00000E+002857 8457  813
8.49829E+054.24915E+04          0          0          6          02857 8457  814
2.00000E+000.00000E+001.29024E-061.29024E-070.00000E+000.00000E+002857 8457  815
8.58242E+054.29121E+04          0          0          6          02857 8457  816
2.00000E+000.00000E+004.03200E-074.03200E-080.00000E+000.00000E+002857 8457  817
8.61129E+054.30565E+04          0          0          6          02857 8457  818
2.00000E+000.00000E+002.52672E-062.52672E-070.00000E+000.00000E+002857 8457  819
8.75829E+054.37915E+04          0          0          6          02857 8457  820
2.00000E+000.00000E+001.13702E-061.13702E-070.00000E+000.00000E+002857 8457  821
8.84242E+054.42121E+04          0          0          6          02857 8457  822
2.00000E+000.00000E+003.50784E-073.50784E-080.00000E+000.00000E+002857 8457  823
8.88929E+054.44465E+04          0          0          6          02857 8457  824
2.00000E+000.00000E+001.44256E-061.44256E-070.00000E+000.00000E+002857 8457  825
8.92129E+054.46065E+04          0          0          6          02857 8457  826
2.00000E+000.00000E+005.32896E-065.32896E-070.00000E+000.00000E+002857 8457  827
8.97342E+054.48671E+04          0          0          6          02857 8457  828
2.00000E+000.00000E+004.63680E-074.63680E-080.00000E+000.00000E+002857 8457  829
9.00542E+054.50271E+04          0          0          6          02857 8457  830
2.00000E+000.00000E+001.50304E-061.50304E-070.00000E+000.00000E+002857 8457  831
9.02079E+054.51040E+04          0          0          6          02857 8457  832
2.00000E+000.00000E+008.55680E-058.55680E-060.00000E+000.00000E+002857 8457  833
9.03659E+054.51830E+04          0          0          6          02857 8457  834
2.00000E+000.00000E+002.17325E-042.17325E-050.00000E+000.00000E+002857 8457  835
9.10492E+054.55246E+04          0          0          6          02857 8457  836
2.00000E+000.00000E+002.46400E-052.46400E-060.00000E+000.00000E+002857 8457  837
9.13409E+054.56705E+04          0          0          6          02857 8457  838
2.00000E+000.00000E+001.87085E-041.87085E-050.00000E+000.00000E+002857 8457  839
9.24129E+054.62065E+04          0          0          6          02857 8457  840
2.00000E+000.00000E+004.46208E-074.46208E-080.00000E+000.00000E+002857 8457  841
9.32542E+054.66271E+04          0          0          6          02857 8457  842
2.00000E+000.00000E+001.12896E-071.12896E-080.00000E+000.00000E+002857 8457  843
9.41529E+054.70765E+04          0          0          6          02857 8457  844
2.00000E+000.00000E+005.10272E-065.10272E-070.00000E+000.00000E+002857 8457  845
9.42229E+054.71115E+04          0          0          6          02857 8457  846
2.00000E+000.00000E+005.40288E-065.40288E-070.00000E+000.00000E+002857 8457  847
9.63929E+054.81965E+04          0          0          6          02857 8457  848
2.00000E+000.00000E+001.43360E-051.43360E-060.00000E+000.00000E+002857 8457  849
9.66659E+054.83330E+04          0          0          6          02857 8457  850
2.00000E+000.00000E+003.38688E-053.38688E-060.00000E+000.00000E+002857 8457  851
9.75072E+054.87536E+04          0          0          6          02857 8457  852
2.00000E+000.00000E+001.12896E-051.12896E-060.00000E+000.00000E+002857 8457  853
9.76409E+054.88205E+04          0          0          6          02857 8457  854
2.00000E+000.00000E+002.85824E-052.85824E-060.00000E+000.00000E+002857 8457  855
9.84822E+054.92411E+04          0          0          6          02857 8457  856
2.00000E+000.00000E+001.03936E-051.03936E-060.00000E+000.00000E+002857 8457  857
1.00453E+065.02265E+04          0          0          6          02857 8457  858
2.00000E+000.00000E+007.61600E-077.61600E-080.00000E+000.00000E+002857 8457  859
1.00523E+065.02615E+04          0          0          6          02857 8457  860
2.00000E+000.00000E+008.06400E-078.06400E-080.00000E+000.00000E+002857 8457  861
1.00673E+065.03365E+04          0          0          6          02857 8457  862
2.00000E+000.00000E+006.23616E-066.23616E-070.00000E+000.00000E+002857 8457  863
1.01294E+065.06471E+04          0          0          6          02857 8457  864
2.00000E+000.00000E+003.04640E-073.04640E-080.00000E+000.00000E+002857 8457  865
1.01364E+065.06821E+04          0          0          6          02857 8457  866
2.00000E+000.00000E+003.22560E-073.22560E-080.00000E+000.00000E+002857 8457  867
1.01653E+065.08265E+04          0          0          6          02857 8457  868
2.00000E+000.00000E+006.27200E-076.27200E-080.00000E+000.00000E+002857 8457  869
1.02693E+065.13465E+04          0          0          6          02857 8457  870
2.00000E+000.00000E+002.19520E-062.19520E-070.00000E+000.00000E+002857 8457  871
1.02853E+065.14265E+04          0          0          6          02857 8457  872
2.00000E+000.00000E+008.27904E-068.27904E-070.00000E+000.00000E+002857 8457  873
1.03534E+065.17671E+04          0          0          6          02857 8457  874
2.00000E+000.00000E+007.16800E-077.16800E-080.00000E+000.00000E+002857 8457  875
1.03823E+065.19115E+04          0          0          6          02857 8457  876
2.00000E+000.00000E+002.82401E-052.82401E-060.00000E+000.00000E+002857 8457  877
1.06973E+065.34865E+04          0          0          6          02857 8457  878
2.00000E+000.00000E+009.56928E-079.56928E-080.00000E+000.00000E+002857 8457  879
1.07814E+065.39071E+04          0          0          6          02857 8457  880
2.00000E+000.00000E+003.33312E-073.33312E-080.00000E+000.00000E+002857 8457  881
1.07953E+065.39765E+04          0          0          6          02857 8457  882
2.00000E+000.00000E+001.03936E-071.03936E-080.00000E+000.00000E+002857 8457  883
1.08794E+065.43971E+04          0          0          6          02857 8457  884
2.00000E+000.00000E+002.68800E-082.68800E-090.00000E+000.00000E+002857 8457  885
1.09153E+065.45765E+04          0          0          6          02857 8457  886
2.00000E+000.00000E+001.25664E-061.25664E-070.00000E+000.00000E+002857 8457  887
1.09994E+065.49971E+04          0          0          6          02857 8457  888
2.00000E+000.00000E+003.69600E-073.69600E-080.00000E+000.00000E+002857 8457  889
1.10123E+065.50615E+04          0          0          6          02857 8457  890
2.00000E+000.00000E+004.11264E-064.11264E-070.00000E+000.00000E+002857 8457  891
1.10964E+065.54821E+04          0          0          6          02857 8457  892
2.00000E+000.00000E+001.46227E-061.46227E-070.00000E+000.00000E+002857 8457  893
0.00000E+009.00000E+00          0          0          6          72857 8457  894
1.00000E+000.00000E+005.78253E+045.78253E+030.00000E+000.00000E+002857 8457  895
2.45800E+034.91600E+01          0          0          6          02857 8457  896
2.00000E+000.00000E+004.94170E-024.94170E-030.00000E+000.00000E+002857 8457  897
9.13700E+031.82740E+02          0          0          6          02857 8457  898
2.00000E+000.00000E+004.16935E-014.16935E-020.00000E+000.00000E+002857 8457  899
6.14870E+041.22974E+03          0          0          6          02857 8457  900
2.00000E+000.00000E+002.40997E-012.40997E-020.00000E+000.00000E+002857 8457  901
6.30000E+041.26000E+03          0          0          6          02857 8457  902
2.00000E+000.00000E+004.15512E-014.15512E-020.00000E+000.00000E+002857 8457  903
7.13000E+041.42600E+03          0          0          6          02857 8457  904
2.00000E+000.00000E+001.42936E-011.42936E-020.00000E+000.00000E+002857 8457  905
7.34000E+041.46800E+03          0          0          6          02857 8457  906
2.00000E+000.00000E+003.61495E-023.61495E-030.00000E+000.00000E+002857 8457  907
5.11000E+050.00000E+00          0          0          6          02857 8457  908
2.00000E+000.00000E+001.06000E-041.06000E-050.00000E+000.00000E+002857 8457  909
                                                                  2857 8  099999
                                                                  2857 0  0    0
                                                                     0 0  0    0
 7.718700+4 1.853510+2         -1          0          2          12858 1451    1
 1.861500+5 1.000000+0          1          1          0          62858 1451    2
 0.000000+0 0.000000+0          0          0          4        3112858 1451    3
 0.000000+0 0.000000+0          0          0         18          22858 1451    4
 77-Ir-187MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2858 1451    5
                      DIST-NOV07                       261107     2858 1451    6
----JEFF-311          MATERIAL 2858                               2858 1451    7
-----RADIOACTIVE DECAY DATA                                       2858 1451    8
------ENDF-6 FORMAT                                               2858 1451    9
******************************************************************2858 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2858 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2858 1451   12
**             Original data taken from:  NUBASE                **2858 1451   13
******************************************************************2858 1451   14
******************************************************************2858 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2858 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2858 1451   17
                                                                  2858 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2858 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2858 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2858 1451   21
******************************************************************2858 1451   22
                                1        451         24          02858 1451   23
                                8        457          5          02858 1451   24
 0.000000+0 0.000000+0          0          0          0          02858 1  099999
                                                                  2858 0  0    0
 7.71870+04 1.85351+02          1          1          0          02858 8457    1
 3.03000-02 6.00000-04          0          0          6          02858 8457    2
 0.00000+00 0.00000+00 1.86150+05 0.00000+00 0.00000+00 0.00000+002858 8457    3
 4.50000+00-1.00000+00          0          0          6          12858 8457    4
 3.00000+00 0.00000+00 1.86150+05 0.00000+00 1.00000+00 0.00000+002858 8457    5
                                                                  2858 8  099999
                                                                  2858 0  0    0
                                                                     0 0  0    0
 7.718800+4 1.863440+2         -1          0          2          12859 1451    1
 0.000000+0 1.000000+0          0          0          0          62859 1451    2
 0.000000+0 0.000000+0          0          0          4        3112859 1451    3
 0.000000+0 0.000000+0          0          0         18          22859 1451    4
 77-Ir-188 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2859 1451    5
                      DIST-NOV07                       261107     2859 1451    6
----JEFF-311          MATERIAL 2859                               2859 1451    7
-----RADIOACTIVE DECAY DATA                                       2859 1451    8
------ENDF-6 FORMAT                                               2859 1451    9
******************************************************************2859 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2859 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2859 1451   12
**             Original data taken from:  NUBASE                **2859 1451   13
******************************************************************2859 1451   14
******************************************************************2859 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2859 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2859 1451   17
                                                                  2859 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2859 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2859 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2859 1451   21
******************************************************************2859 1451   22
                                1        451         24          02859 1451   23
                                8        457          5          02859 1451   24
 0.000000+0 0.000000+0          0          0          0          02859 1  099999
                                                                  2859 0  0    0
 7.71880+04 1.86344+02          0          0          0          02859 8457    1
 1.49400+05 1.80000+03          0          0          6          02859 8457    2
 9.36133+05 0.00000+00 9.36133+05 0.00000+00 0.00000+00 0.00000+002859 8457    3
 1.00000+00-1.00000+00          0          0          6          12859 8457    4
 2.00000+00 0.00000+00 2.80840+06 0.00000+00 1.00000+00 0.00000+002859 8457    5
                                                                  2859 8  099999
                                                                  2859 0  0    0
                                                                     0 0  0    0
 7.718800+4 1.863440+2         -1          0          2          12860 1451    1
 9.700000+5 1.000000+0          1          1          0          62860 1451    2
 0.000000+0 0.000000+0          0          0          4        3112860 1451    3
 0.000000+0 0.000000+0          0          0         18          22860 1451    4
 77-Ir-188MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2860 1451    5
                      DIST-NOV07                       261107     2860 1451    6
----JEFF-311          MATERIAL 2860                               2860 1451    7
-----RADIOACTIVE DECAY DATA                                       2860 1451    8
------ENDF-6 FORMAT                                               2860 1451    9
******************************************************************2860 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2860 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2860 1451   12
**             Original data taken from:  NUBASE                **2860 1451   13
******************************************************************2860 1451   14
******************************************************************2860 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2860 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2860 1451   17
                                                                  2860 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2860 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2860 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2860 1451   21
******************************************************************2860 1451   22
                                1        451         24          02860 1451   23
                                8        457          5          02860 1451   24
 0.000000+0 0.000000+0          0          0          0          02860 1  099999
                                                                  2860 0  0    0
 7.71880+04 1.86344+02          1          1          0          02860 8457    1
 4.20000-03 2.00000-04          0          0          6          02860 8457    2
 0.00000+00 0.00000+00 9.70000+05 0.00000+00 0.00000+00 0.00000+002860 8457    3
 7.00000+00 1.00000+00          0          0          6          12860 8457    4
 3.00000+00 0.00000+00 9.70000+05 0.00000+00 1.00000+00 0.00000+002860 8457    5
                                                                  2860 8  099999
                                                                  2860 0  0    0
                                                                     0 0  0    0
 7.718900+4 1.873350+2         -1          0          2          12861 1451    1
 0.000000+0 1.000000+0          0          0          0          62861 1451    2
 0.000000+0 0.000000+0          0          0          4        3112861 1451    3
 0.000000+0 0.000000+0          0          0         47          22861 1451    4
 77-Ir-189 ENSDF      EVAL-SEP03 CONVERSION OF ENSDF              2861 1451    5
 /ENSDF/              DIST-NOV07                       261107     2861 1451    6
----JEFF-311          MATERIAL 2861                               2861 1451    7
-----RADIOACTIVE DECAY DATA                                       2861 1451    8
------ENDF-6 FORMAT                                               2861 1451    9
******************************************************************2861 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2861 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2861 1451   12
**             Original data taken from:  ENSDF                 **2861 1451   13
******************************************************************2861 1451   14
******************************************************************2861 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2861 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2861 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2861 1451   18
******************************************************************2861 1451   19
189IR DECAY 13.2 D         1                I(min) = 0.0E+00 %    2861 1451   20
         Ex = 0.0         keV                     1 decay mode(s) 2861 1451   21
                                                                  2861 1451   22
189IR EC DECAY              Q =   532.0000 keV      13.0000       2861 1451   23
         Branching                100.0000 %         0.0000       2861 1451   24
                         Br*Q =   532.0000 keV      13.0000       2861 1451   25
                                              1 isomeric state(s) 2861 1451   26
         Ex =      0.0000 keV      92.5134 %                      2861 1451   27
         Ex =     30.8080 keV       7.4866 %                      2861 1451   28
                                                                  2861 1451   29
Individual beta+ transitions                                      2861 1451   30
Final level    end point    shape    av.energy        intensity   2861 1451   31
                                                                  2861 1451   32
         Mean alpha    energy       0.0000 keV       0.0000       2861 1451   33
         Mean beta     energy       0.0000 keV       0.0000       2861 1451   34
         Mean conv. e- energy      32.4235 keV       2.0645       2861 1451   35
         Mean Auger e- energy       7.8327 keV       0.8338       2861 1451   36
         Mean gamma    energy      24.9809 keV                    2861 1451   37
         Mean X        energy      53.9395 keV       2.3553       2861 1451   38
         Mean recoil   energy       0.0000 keV       0.0000       2861 1451   39
         Mean neutrino energy     406.2663 keV      38.8583       2861 1451   40
         Mean neutron  energy       0.0000 keV       0.0000       2861 1451   41
         Total         energy     525.4429 keV      39.0237       2861 1451   42
         Q effective              529.6935 keV      13.0000       2861 1451   43
         diff. mode                -4.2506 keV      -0.8025 %     2861 1451   44
                                                                  2861 1451   45
         Mean e- bind. energy      69.2776 keV                    2861 1451   46
         diff. atomic              -7.5053 keV     -10.8337 %     2861 1451   47
         diff. nuclear              3.2548 keV       0.6145 %     2861 1451   48
                                                                  2861 1451   49
         B+ fraction                0.0000 %         0.0000       2861 1451   50
                                                                  2861 1451   51
                                1        451         53          02861 1451   52
                                8        457        302          02861 1451   53
 0.000000+0 0.000000+0          0          0          0          02861 1  099999
                                                                  2861 0  0    0
 7.71890+04 1.87335+02          0          0          0          42861 8457    1
 1.14048+06 8.64000+03          0          0          6          02861 8457    2
 4.02562+04 2.22650+03 7.89204+04 2.81431+03 0.00000+00 0.00000+002861 8457    3
 1.50000+00 1.00000+00          0          0         12          22861 8457    4
 2.00000+00 0.00000+00 5.32000+05 1.30000+04 9.25134-01 0.00000+002861 8457    5
 2.00000+00 1.00000+00 5.01192+05 1.30000+04 7.48662-02 0.00000+002861 8457    6
 0.00000+00 0.00000+00          0          0          6         262861 8457    7
 1.00000-02 0.00000+00 2.49809+04 1.54044+03 0.00000+00 0.00000+002861 8457    8
 2.56500+04 1.00000+02          0          0         12          02861 8457    9
 2.00000+00 0.00000+00 2.40000-02 3.84187-03 0.00000+00 0.00000+002861 8457   10
 8.20000+01 1.10000+01 0.00000+00 0.00000+00 6.20000+01 6.28169+002861 8457   11
 3.08100+04 2.10000+01          0          0         12          02861 8457   12
 2.00000+00 0.00000+00 2.28922-05 0.00000+00 0.00000+00 0.00000+002861 8457   13
 3.25000+05 8.00000+03 0.00000+00 0.00000+00 2.27000+05 9.07613+032861 8457   14
 3.33100+04 4.00000+01          0          0         12          02861 8457   15
 2.00000+00 0.00000+00 6.78000-03 1.07948-03 0.00000+00 0.00000+002861 8457   16
 7.39000+02 0.00000+00 0.00000+00 0.00000+00 5.54000+02 1.66200+012861 8457   17
 3.61700+04 3.00000+01          0          0         12          02861 8457   18
 2.00000+00 0.00000+00 6.72000-01 9.00880-02 0.00000+00 0.00000+002861 8457   19
 2.10000+01 0.00000+00 0.00000+00 0.00000+00 1.61000+01 4.83000-012861 8457   20
 5.65000+04 3.00000+01          0          0         12          02861 8457   21
 2.00000+00 0.00000+00 1.50000-01 3.35410-02 0.00000+00 0.00000+002861 8457   22
 5.36000+00 0.00000+00 0.00000+00 0.00000+00 4.13000+00 1.23900-012861 8457   23
 5.90500+04 2.00000+01          0          0         12          02861 8457   24
 2.00000+00 0.00000+00 1.20000+00 1.69706-01 0.00000+00 0.00000+002861 8457   25
 4.90000+00 1.30000-01 0.00000+00 0.00000+00 3.77000+00 1.44539-012861 8457   26
 5.93000+04 1.00000+02          0          0         12          02861 8457   27
 2.00000+00 0.00000+00 6.00000-02 6.00000-03 0.00000+00 0.00000+002861 8457   28
 2.10000+01 0.00000+00 0.00000+00 0.00000+00 1.70000+01 6.02164+002861 8457   29
 6.95280+04 2.00000+01          0          0         12          02861 8457   30
 2.00000+00 0.00000+00 3.54000+00 5.04892-01 0.00000+00 0.00000+002861 8457   31
 8.48000+00 2.20000-01 0.00000+00 0.00000+00 6.41000+00 2.50159-012861 8457   32
 9.52400+04 4.00000+01          0          0         12          02861 8457   33
 2.00000+00 0.00000+00 3.84000-01 4.87295-02 0.00000+00 0.00000+002861 8457   34
 6.59000+00 0.00000+00 5.14000+00 1.54200-01 1.11000+00 3.33000-022861 8457   35
 1.38240+05 5.00000+01          0          0         12          02861 8457   36
 2.00000+00 0.00000+00 6.84000-02 1.03743-02 0.00000+00 0.00000+002861 8457   37
 1.89000+00 1.10000-01 1.32000+00 1.64828-01 4.30000-01 5.16373-022861 8457   38
 1.47090+05 5.00000+01          0          0         12          02861 8457   39
 2.00000+00 0.00000+00 1.08000-01 1.36821-02 0.00000+00 0.00000+002861 8457   40
 1.51000+00 1.30000-01 1.05000+00 1.72894-01 3.50000-01 5.10906-022861 8457   41
 1.49840+05 5.00000+01          0          0         12          02861 8457   42
 2.00000+00 0.00000+00 8.46000-02 1.03717-02 0.00000+00 0.00000+002861 8457   43
 9.30000-01 0.00000+00 3.56000-01 1.06800-02 4.31000-01 1.29300-022861 8457   44
 1.64020+05 5.00000+01          0          0         12          02861 8457   45
 2.00000+00 0.00000+00 7.38000-02 8.21124-03 0.00000+00 0.00000+002861 8457   46
 1.05000+00 1.40000-01 7.30000-01 1.71405-01 2.40000-01 4.06428-022861 8457   47
 1.80670+05 5.00000+01          0          0         12          02861 8457   48
 2.00000+00 0.00000+00 2.94000-02 4.20043-03 0.00000+00 0.00000+002861 8457   49
 8.80000-01 1.80000-01 6.70000-01 2.01007-01 1.60000-01 5.02299-022861 8457   50
 1.85890+05 5.00000+01          0          0         12          02861 8457   51
 2.00000+00 0.00000+00 1.80000-01 2.54558-02 0.00000+00 0.00000+002861 8457   52
 6.90000-01 5.00000-02 4.90000-01 5.21161-02 1.53000-01 1.19192-022861 8457   53
 1.88550+05 5.00000+01          0          0         12          02861 8457   54
 2.00000+00 0.00000+00 5.16000-02 6.65324-03 0.00000+00 0.00000+002861 8457   55
 7.80000-01 1.40000-01 6.00000-01 1.61009-01 1.40000-01 3.02926-022861 8457   56
 1.97330+05 5.00000+01          0          0         12          02861 8457   57
 2.00000+00 0.00000+00 2.64000-01 2.89993-02 0.00000+00 0.00000+002861 8457   58
 3.52000-01 0.00000+00 3.10000-01 1.30332-01 1.30000-01 3.02524-022861 8457   59
 2.06370+05 4.00000+01          0          0         12          02861 8457   60
 2.00000+00 0.00000+00 7.98000-02 8.52528-03 0.00000+00 0.00000+002861 8457   61
 4.80000-01 7.00000-02 3.50000-01 7.07831-02 1.05000-01 1.43500-022861 8457   62
 2.16680+05 5.00000+01          0          0         12          02861 8457   63
 2.00000+00 0.00000+00 5.16000-01 5.69083-02 0.00000+00 0.00000+002861 8457   64
 2.57000-01 0.00000+00 1.39000-01 4.17000-03 8.93000-02 2.67900-032861 8457   65
 2.19400+05 4.00000+01          0          0         12          02861 8457   66
 2.00000+00 0.00000+00 5.28000-01 5.79986-02 0.00000+00 0.00000+002861 8457   67
 2.47000-01 0.00000+00 1.35000-01 4.05000-03 8.48000-02 2.54400-032861 8457   68
 2.33590+05 9.00000+01          0          0         12          02861 8457   69
 2.00000+00 0.00000+00 3.00000-01 3.23110-02 0.00000+00 0.00000+002861 8457   70
 3.40000-01 5.00000-02 2.50000-01 5.05594-02 6.80000-02 9.22830-032861 8457   71
 2.45080+05 9.00000+01          0          0         12          02861 8457   72
 2.00000+00 0.00000+00 6.00000+00 6.00000-01 0.00000+00 0.00000+002861 8457   73
 1.72000-01 0.00000+00 1.00700-01 3.02100-03 5.42000-02 1.62600-032861 8457   74
 2.75890+05 1.00000+02          0          0         12          02861 8457   75
 2.00000+00 0.00000+00 5.40000-01 6.17738-02 0.00000+00 0.00000+002861 8457   76
 1.74000-01 1.60000-02 1.26000-01 1.54689-02 3.68000-02 2.73291-032861 8457   77
 3.43200+05 1.00000+02          0          0         12          02861 8457   78
 2.00000+00 0.00000+00 5.46000-02 6.54000-03 0.00000+00 0.00000+002861 8457   79
 1.85000-01 0.00000+00 1.53000-01 4.59000-03 2.45000-02 7.35000-042861 8457   80
 4.02780+05 1.00000+02          0          0         12          02861 8457   81
 2.00000+00 0.00000+00 6.60000-03 8.91964-04 0.00000+00 0.00000+002861 8457   82
 1.21000-01 0.00000+00 1.00200-01 3.00600-03 1.59000-02 4.77000-042861 8457   83
 4.38500+05 1.00000+02          0          0         12          02861 8457   84
 2.00000+00 0.00000+00 3.60000-03 1.25284-03 0.00000+00 0.00000+002861 8457   85
 9.67000-02 0.00000+00 8.02000-02 2.40600-03 1.27000-02 3.81000-042861 8457   86
 0.00000+00 2.00000+00          0          0          6          72861 8457   87
 1.00000-02 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002861 8457   88
 9.34800+04 1.30003+04          0          0          6          02861 8457   89
 2.00000+00 1.00000+00 7.60000-02 8.00000-03 0.00000+00 0.00000+002861 8457   90
 2.56102+05 1.30000+04          0          0          6          02861 8457   91
 2.00000+00 1.00000+00 1.02000+01 1.00000+00 0.00000+00 0.00000+002861 8457   92
 2.98470+05 1.30000+04          0          0          6          02861 8457   93
 2.00000+00 1.00000+00 1.11000+00 1.20000-01 0.00000+00 0.00000+002861 8457   94
 4.36755+05 1.30000+04          0          0          6          02861 8457   95
 2.00000+00 1.00000+00 1.17000+01 1.20000+00 0.00000+00 0.00000+002861 8457   96
 4.62471+05 1.30000+04          0          0          6          02861 8457   97
 2.00000+00 1.00000+00 3.60000+01 4.00000+00 0.00000+00 0.00000+002861 8457   98
 4.95809+05 1.30000+04          0          0          6          02861 8457   99
 2.00000+00 1.00000+00 2.30000+00 1.60000+00 0.00000+00 0.00000+002861 8457  100
 5.32000+05 1.30000+04          0          0          6          02861 8457  101
 2.00000+00 1.00000+00 3.90000+01 6.00000+00 0.00000+00 0.00000+002861 8457  102
 0.00000+00 8.00000+00          0          0          6         942861 8457  103
 1.00000-02 0.00000+00 4.02562+04 2.22650+03 0.00000+00 0.00000+002861 8457  104
 6.88000+03 0.00000+00          0          0          6          02861 8457  105
 2.00000+00 0.00000+00 9.16715+01 6.28497+00 0.00000+00 0.00000+002861 8457  106
 1.26820+04 1.00001+02          0          0          6          02861 8457  107
 2.00000+00 0.00000+00 1.48800+00 2.81897-01 0.00000+00 0.00000+002861 8457  108
 1.78420+04 2.10038+01          0          0          6          02861 8457  109
 2.00000+00 0.00000+00 5.19654+00 2.07773-01 0.00000+00 0.00000+002861 8457  110
 2.03420+04 4.00020+01          0          0          6          02861 8457  111
 2.00000+00 0.00000+00 3.75612+00 6.08557-01 0.00000+00 0.00000+002861 8457  112
 2.13692+04 4.00031+01          0          0          6          02861 8457  113
 2.00000+00 0.00000+00 1.97376+00 2.57373-01 0.00000+00 0.00000+002861 8457  114
 2.26015+04 1.00001+02          0          0          6          02861 8457  115
 2.00000+00 0.00000+00 3.52800-01 6.78049-02 0.00000+00 0.00000+002861 8457  116
 2.32020+04 3.00027+01          0          0          6          02861 8457  117
 2.00000+00 0.00000+00 1.08192+01 1.48629+00 0.00000+00 0.00000+002861 8457  118
 2.77615+04 2.10038+01          0          0          6          02861 8457  119
 2.00000+00 0.00000+00 1.66884+00 6.48419-02 0.00000+00 0.00000+002861 8457  120
 3.02615+04 4.00020+01          0          0          6          02861 8457  121
 2.00000+00 0.00000+00 9.49200-01 1.53787-01 0.00000+00 0.00000+002861 8457  122
 3.31215+04 3.00027+01          0          0          6          02861 8457  123
 2.00000+00 0.00000+00 2.48640+00 3.41570-01 0.00000+00 0.00000+002861 8457  124
 4.35320+04 3.00027+01          0          0          6          02861 8457  125
 2.00000+00 0.00000+00 6.19500-01 1.39766-01 0.00000+00 0.00000+002861 8457  126
 4.60820+04 2.00040+01          0          0          6          02861 8457  127
 2.00000+00 0.00000+00 4.52400+00 6.62884-01 0.00000+00 0.00000+002861 8457  128
 4.63320+04 1.00001+02          0          0          6          02861 8457  129
 2.00000+00 0.00000+00 1.02000+00 3.75420-01 0.00000+00 0.00000+002861 8457  130
 4.83000+04 0.00000+00          0          0          6          02861 8457  131
 2.00000+00 0.00000+00 3.15882+00 1.47597+00 0.00000+00 0.00000+002861 8457  132
 5.34515+04 3.00027+01          0          0          6          02861 8457  133
 2.00000+00 0.00000+00 1.41900-01 3.20141-02 0.00000+00 0.00000+002861 8457  134
 5.58457+04 3.00042+01          0          0          6          02861 8457  135
 2.00000+00 0.00000+00 4.35000-02 9.81405-03 0.00000+00 0.00000+002861 8457  136
 5.60015+04 2.00040+01          0          0          6          02861 8457  137
 2.00000+00 0.00000+00 1.04160+00 1.52879-01 0.00000+00 0.00000+002861 8457  138
 5.62515+04 1.00001+02          0          0          6          02861 8457  139
 2.00000+00 0.00000+00 2.52000-01 9.95399-02 0.00000+00 0.00000+002861 8457  140
 5.65600+04 2.00040+01          0          0          6          02861 8457  141
 2.00000+00 0.00000+00 2.26914+01 3.35533+00 0.00000+00 0.00000+002861 8457  142
 5.83957+04 2.00062+01          0          0          6          02861 8457  143
 2.00000+00 0.00000+00 3.19200-01 4.69045-02 0.00000+00 0.00000+002861 8457  144
 5.86457+04 1.00001+02          0          0          6          02861 8457  145
 2.00000+00 0.00000+00 7.20000-02 3.67764-02 0.00000+00 0.00000+002861 8457  146
 6.43692+04 5.00025+01          0          0          6          02861 8457  147
 2.00000+00 0.00000+00 9.02880-02 1.77379-02 0.00000+00 0.00000+002861 8457  148
 6.64795+04 2.00040+01          0          0          6          02861 8457  149
 2.00000+00 0.00000+00 5.66400+00 8.37561-01 0.00000+00 0.00000+002861 8457  150
 6.88737+04 2.00062+01          0          0          6          02861 8457  151
 2.00000+00 0.00000+00 1.68858+00 2.49743-01 0.00000+00 0.00000+002861 8457  152
 7.32192+04 5.00025+01          0          0          6          02861 8457  153
 2.00000+00 0.00000+00 1.13400-01 2.35595-02 0.00000+00 0.00000+002861 8457  154
 7.59692+04 5.00025+01          0          0          6          02861 8457  155
 2.00000+00 0.00000+00 3.01176-02 3.80126-03 0.00000+00 0.00000+002861 8457  156
 8.22720+04 4.00020+01          0          0          6          02861 8457  157
 2.00000+00 0.00000+00 4.26240-01 5.55806-02 0.00000+00 0.00000+002861 8457  158
 9.01492+04 5.00025+01          0          0          6          02861 8457  159
 2.00000+00 0.00000+00 5.38740-02 1.39980-02 0.00000+00 0.00000+002861 8457  160
 9.21915+04 4.00020+01          0          0          6          02861 8457  161
 2.00000+00 0.00000+00 1.00224-01 1.30690-02 0.00000+00 0.00000+002861 8457  162
 9.45857+04 4.00031+01          0          0          6          02861 8457  163
 2.00000+00 0.00000+00 3.08736-02 4.02584-03 0.00000+00 0.00000+002861 8457  164
 1.06799+05 5.00025+01          0          0          6          02861 8457  165
 2.00000+00 0.00000+00 1.96980-02 6.54552-03 0.00000+00 0.00000+002861 8457  166
 1.12019+05 5.00025+01          0          0          6          02861 8457  167
 2.00000+00 0.00000+00 8.82000-02 1.56072-02 0.00000+00 0.00000+002861 8457  168
 1.14679+05 5.00025+01          0          0          6          02861 8457  169
 2.00000+00 0.00000+00 3.09600-02 9.21737-03 0.00000+00 0.00000+002861 8457  170
 1.23459+05 5.00025+01          0          0          6          02861 8457  171
 2.00000+00 0.00000+00 8.18400-02 3.55627-02 0.00000+00 0.00000+002861 8457  172
 1.25272+05 5.00016+01          0          0          6          02861 8457  173
 2.00000+00 0.00000+00 2.94120-02 5.68990-03 0.00000+00 0.00000+002861 8457  174
 1.32499+05 4.00031+01          0          0          6          02861 8457  175
 2.00000+00 0.00000+00 2.79300-02 6.38818-03 0.00000+00 0.00000+002861 8457  176
 1.34122+05 5.00016+01          0          0          6          02861 8457  177
 2.00000+00 0.00000+00 3.78000-02 7.30602-03 0.00000+00 0.00000+002861 8457  178
 1.35192+05 5.00016+01          0          0          6          02861 8457  179
 2.00000+00 0.00000+00 7.11360-03 1.37235-03 0.00000+00 0.00000+002861 8457  180
 1.36872+05 5.00016+01          0          0          6          02861 8457  181
 2.00000+00 0.00000+00 3.64626-02 4.60208-03 0.00000+00 0.00000+002861 8457  182
 1.37586+05 5.00025+01          0          0          6          02861 8457  183
 2.00000+00 0.00000+00 2.18880-03 3.95762-04 0.00000+00 0.00000+002861 8457  184
 1.42809+05 5.00025+01          0          0          6          02861 8457  185
 2.00000+00 0.00000+00 7.17240-02 8.19769-03 0.00000+00 0.00000+002861 8457  186
 1.44042+05 5.00016+01          0          0          6          02861 8457  187
 2.00000+00 0.00000+00 9.28800-03 1.77251-03 0.00000+00 0.00000+002861 8457  188
 1.45529+05 4.00031+01          0          0          6          02861 8457  189
 2.00000+00 0.00000+00 7.12800-02 8.11657-03 0.00000+00 0.00000+002861 8457  190
 1.46436+05 5.00025+01          0          0          6          02861 8457  191
 2.00000+00 0.00000+00 2.81880-03 4.55602-04 0.00000+00 0.00000+002861 8457  192
 1.46792+05 5.00016+01          0          0          6          02861 8457  193
 2.00000+00 0.00000+00 9.22140-03 1.16387-03 0.00000+00 0.00000+002861 8457  194
 1.49186+05 5.00025+01          0          0          6          02861 8457  195
 2.00000+00 0.00000+00 2.78334-03 3.51296-04 0.00000+00 0.00000+002861 8457  196
 1.51052+05 5.00016+01          0          0          6          02861 8457  197
 2.00000+00 0.00000+00 1.77120-02 3.58891-03 0.00000+00 0.00000+002861 8457  198
 1.59719+05 9.00014+01          0          0          6          02861 8457  199
 2.00000+00 0.00000+00 7.50000-02 1.71847-02 0.00000+00 0.00000+002861 8457  200
 1.60972+05 5.00016+01          0          0          6          02861 8457  201
 2.00000+00 0.00000+00 4.28040-03 8.87665-04 0.00000+00 0.00000+002861 8457  202
 1.63366+05 5.00025+01          0          0          6          02861 8457  203
 2.00000+00 0.00000+00 1.30626-03 1.91316-04 0.00000+00 0.00000+002861 8457  204
 1.67702+05 5.00016+01          0          0          6          02861 8457  205
 2.00000+00 0.00000+00 4.70400-03 1.62250-03 0.00000+00 0.00000+002861 8457  206
 1.71209+05 9.00014+01          0          0          6          02861 8457  207
 2.00000+00 0.00000+00 6.04200-01 6.30803-02 0.00000+00 0.00000+002861 8457  208
 1.72922+05 5.00016+01          0          0          6          02861 8457  209
 2.00000+00 0.00000+00 2.75400-02 4.44658-03 0.00000+00 0.00000+002861 8457  210
 1.75582+05 5.00016+01          0          0          6          02861 8457  211
 2.00000+00 0.00000+00 7.22400-03 1.81958-03 0.00000+00 0.00000+002861 8457  212
 1.77622+05 5.00016+01          0          0          6          02861 8457  213
 2.00000+00 0.00000+00 1.11720-03 3.62199-04 0.00000+00 0.00000+002861 8457  214
 1.80016+05 5.00025+01          0          0          6          02861 8457  215
 2.00000+00 0.00000+00 3.41040-04 6.27660-05 0.00000+00 0.00000+002861 8457  216
 1.82842+05 5.00016+01          0          0          6          02861 8457  217
 2.00000+00 0.00000+00 6.66000-03 1.10392-03 0.00000+00 0.00000+002861 8457  218
 1.84362+05 5.00016+01          0          0          6          02861 8457  219
 2.00000+00 0.00000+00 3.43200-02 8.83169-03 0.00000+00 0.00000+002861 8457  220
 1.85236+05 5.00025+01          0          0          6          02861 8457  221
 2.00000+00 0.00000+00 2.01600-03 2.96410-04 0.00000+00 0.00000+002861 8457  222
 1.85502+05 5.00016+01          0          0          6          02861 8457  223
 2.00000+00 0.00000+00 1.70280-03 4.70339-04 0.00000+00 0.00000+002861 8457  224
 1.87896+05 5.00025+01          0          0          6          02861 8457  225
 2.00000+00 0.00000+00 5.16000-04 7.98137-05 0.00000+00 0.00000+002861 8457  226
 1.93402+05 4.00020+01          0          0          6          02861 8457  227
 2.00000+00 0.00000+00 8.37900-03 1.45349-03 0.00000+00 0.00000+002861 8457  228
 1.94282+05 5.00016+01          0          0          6          02861 8457  229
 2.00000+00 0.00000+00 8.18400-03 2.06967-03 0.00000+00 0.00000+002861 8457  230
 1.96676+05 5.00025+01          0          0          6          02861 8457  231
 2.00000+00 0.00000+00 2.48160-03 3.11887-04 0.00000+00 0.00000+002861 8457  232
 2.02019+05 1.00001+02          0          0          6          02861 8457  233
 2.00000+00 0.00000+00 6.80400-02 1.14175-02 0.00000+00 0.00000+002861 8457  234
 2.03322+05 4.00020+01          0          0          6          02861 8457  235
 2.00000+00 0.00000+00 1.99500-03 3.26067-04 0.00000+00 0.00000+002861 8457  236
 2.03712+05 5.00016+01          0          0          6          02861 8457  237
 2.00000+00 0.00000+00 4.60788-02 5.26657-03 0.00000+00 0.00000+002861 8457  238
 2.05716+05 4.00031+01          0          0          6          02861 8457  239
 2.00000+00 0.00000+00 6.12864-04 6.96763-05 0.00000+00 0.00000+002861 8457  240
 2.06432+05 4.00020+01          0          0          6          02861 8457  241
 2.00000+00 0.00000+00 4.47744-02 5.09841-03 0.00000+00 0.00000+002861 8457  242
 2.13632+05 5.00016+01          0          0          6          02861 8457  243
 2.00000+00 0.00000+00 1.15068-02 1.31517-03 0.00000+00 0.00000+002861 8457  244
 2.16026+05 5.00025+01          0          0          6          02861 8457  245
 2.00000+00 0.00000+00 3.42624-03 3.91602-04 0.00000+00 0.00000+002861 8457  246
 2.16352+05 4.00020+01          0          0          6          02861 8457  247
 2.00000+00 0.00000+00 1.11936-02 1.27460-03 0.00000+00 0.00000+002861 8457  248
 2.18746+05 4.00031+01          0          0          6          02861 8457  249
 2.00000+00 0.00000+00 3.33168-03 3.79375-04 0.00000+00 0.00000+002861 8457  250
 2.20622+05 9.00009+01          0          0          6          02861 8457  251
 2.00000+00 0.00000+00 2.04000-02 3.53440-03 0.00000+00 0.00000+002861 8457  252
 2.30542+05 9.00009+01          0          0          6          02861 8457  253
 2.00000+00 0.00000+00 4.89000-03 8.34147-04 0.00000+00 0.00000+002861 8457  254
 2.32112+05 9.00009+01          0          0          6          02861 8457  255
 2.00000+00 0.00000+00 3.25200-01 3.39519-02 0.00000+00 0.00000+002861 8457  256
 2.32936+05 9.00014+01          0          0          6          02861 8457  257
 2.00000+00 0.00000+00 1.46700-03 1.67920-04 0.00000+00 0.00000+002861 8457  258
 2.42032+05 9.00009+01          0          0          6          02861 8457  259
 2.00000+00 0.00000+00 8.10000-02 8.45665-03 0.00000+00 0.00000+002861 8457  260
 2.44426+05 9.00014+01          0          0          6          02861 8457  261
 2.00000+00 0.00000+00 2.40000-02 2.50567-03 0.00000+00 0.00000+002861 8457  262
 2.62922+05 1.00001+02          0          0          6          02861 8457  263
 2.00000+00 0.00000+00 1.98720-02 2.71029-03 0.00000+00 0.00000+002861 8457  264
 2.69329+05 1.00001+02          0          0          6          02861 8457  265
 2.00000+00 0.00000+00 8.35380-03 1.03153-03 0.00000+00 0.00000+002861 8457  266
 2.72842+05 1.00001+02          0          0          6          02861 8457  267
 2.00000+00 0.00000+00 4.80600-03 6.54239-04 0.00000+00 0.00000+002861 8457  268
 2.75236+05 1.00001+02          0          0          6          02861 8457  269
 2.00000+00 0.00000+00 1.43100-03 1.73406-04 0.00000+00 0.00000+002861 8457  270
 3.28909+05 1.00001+02          0          0          6          02861 8457  271
 2.00000+00 0.00000+00 6.61320-04 9.15503-05 0.00000+00 0.00000+002861 8457  272
 3.30232+05 1.00001+02          0          0          6          02861 8457  273
 2.00000+00 0.00000+00 1.33770-03 1.65179-04 0.00000+00 0.00000+002861 8457  274
 3.40152+05 1.00001+02          0          0          6          02861 8457  275
 2.00000+00 0.00000+00 3.05760-04 3.77552-05 0.00000+00 0.00000+002861 8457  276
 3.42546+05 1.00001+02          0          0          6          02861 8457  277
 2.00000+00 0.00000+00 9.28200-05 1.14614-05 0.00000+00 0.00000+002861 8457  278
 3.64629+05 1.00001+02          0          0          6          02861 8457  279
 2.00000+00 0.00000+00 2.88720-04 1.00850-04 0.00000+00 0.00000+002861 8457  280
 3.89812+05 1.00001+02          0          0          6          02861 8457  281
 2.00000+00 0.00000+00 1.04940-04 1.45274-05 0.00000+00 0.00000+002861 8457  282
 3.99732+05 1.00001+02          0          0          6          02861 8457  283
 2.00000+00 0.00000+00 2.40240-05 3.32578-06 0.00000+00 0.00000+002861 8457  284
 4.02126+05 1.00001+02          0          0          6          02861 8457  285
 2.00000+00 0.00000+00 7.32600-06 1.01418-06 0.00000+00 0.00000+002861 8457  286
 4.25532+05 1.00001+02          0          0          6          02861 8457  287
 2.00000+00 0.00000+00 4.57200-05 1.59700-05 0.00000+00 0.00000+002861 8457  288
 4.35452+05 1.00001+02          0          0          6          02861 8457  289
 2.00000+00 0.00000+00 1.04400-05 3.64670-06 0.00000+00 0.00000+002861 8457  290
 4.37846+05 1.00001+02          0          0          6          02861 8457  291
 2.00000+00 0.00000+00 3.18240-06 1.11162-06 0.00000+00 0.00000+002861 8457  292
 0.00000+00 9.00000+00          0          0          6          42861 8457  293
 1.00000-02 0.00000+00 5.39395+04 2.35529+03 0.00000+00 0.00000+002861 8457  294
 8.91000+03 0.00000+00          0          0          6          02861 8457  295
 2.00000+00 0.00000+00 4.31395+01 4.63487+00 0.00000+00 0.00000+002861 8457  296
 6.14867+04 7.00000-01          0          0          6          02861 8457  297
 2.00000+00 0.00000+00 2.24384+01 1.71672+00 0.00000+00 0.00000+002861 8457  298
 6.30005+04 7.00000-01          0          0          6          02861 8457  299
 2.00000+00 0.00000+00 3.87538+01 2.93582+00 0.00000+00 0.00000+002861 8457  300
 7.14000+04 0.00000+00          0          0          6          02861 8457  301
 2.00000+00 0.00000+00 1.66443+01 1.28492+00 0.00000+00 0.00000+002861 8457  302
                                                                  2861 8  099999
                                                                  2861 0  0    0
                                                                     0 0  0    0
 7.718900+4 1.873350+2         -1          0          2          12862 1451    1
 3.721700+5 1.000000+0          1          1          0          62862 1451    2
 0.000000+0 0.000000+0          0          0          4        3112862 1451    3
 0.000000+0 0.000000+0          0          0         18          22862 1451    4
 77-Ir-189MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2862 1451    5
                      DIST-NOV07                       261107     2862 1451    6
----JEFF-311          MATERIAL 2862                               2862 1451    7
-----RADIOACTIVE DECAY DATA                                       2862 1451    8
------ENDF-6 FORMAT                                               2862 1451    9
******************************************************************2862 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2862 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2862 1451   12
**             Original data taken from:  NUBASE                **2862 1451   13
******************************************************************2862 1451   14
******************************************************************2862 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2862 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2862 1451   17
                                                                  2862 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2862 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2862 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2862 1451   21
******************************************************************2862 1451   22
                                1        451         24          02862 1451   23
                                8        457          5          02862 1451   24
 0.000000+0 0.000000+0          0          0          0          02862 1  099999
                                                                  2862 0  0    0
 7.71890+04 1.87335+02          1          1          0          02862 8457    1
 1.33000-02 3.00000-04          0          0          6          02862 8457    2
 0.00000+00 0.00000+00 3.72170+05 0.00000+00 0.00000+00 0.00000+002862 8457    3
 5.50000+00-1.00000+00          0          0          6          12862 8457    4
 3.00000+00 0.00000+00 3.72170+05 0.00000+00 1.00000+00 0.00000+002862 8457    5
                                                                  2862 8  099999
                                                                  2862 0  0    0
                                                                     0 0  0    0
 7.718900+4 1.873350+2         -1          0          2          12863 1451    1
 2.333200+6 1.000000+0          2          2          0          62863 1451    2
 0.000000+0 0.000000+0          0          0          4        3112863 1451    3
 0.000000+0 0.000000+0          0          0         18          22863 1451    4
 77-Ir-189NCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2863 1451    5
                      DIST-NOV07                       261107     2863 1451    6
----JEFF-311          MATERIAL 2863                               2863 1451    7
-----RADIOACTIVE DECAY DATA                                       2863 1451    8
------ENDF-6 FORMAT                                               2863 1451    9
******************************************************************2863 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2863 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2863 1451   12
**             Original data taken from:  NUBASE                **2863 1451   13
******************************************************************2863 1451   14
******************************************************************2863 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2863 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2863 1451   17
                                                                  2863 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2863 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2863 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2863 1451   21
******************************************************************2863 1451   22
                                1        451         24          02863 1451   23
                                8        457          5          02863 1451   24
 0.000000+0 0.000000+0          0          0          0          02863 1  099999
                                                                  2863 0  0    0
 7.71890+04 1.87335+02          2          2          0          02863 8457    1
 3.70000-03 2.00000-04          0          0          6          02863 8457    2
 0.00000+00 0.00000+00 1.96103+06 0.00000+00 0.00000+00 0.00000+002863 8457    3
 1.25000+01 1.00000+00          0          0          6          12863 8457    4
 3.00000+00 1.00000+00 1.96103+06 0.00000+00 1.00000+00 0.00000+002863 8457    5
                                                                  2863 8  099999
                                                                  2863 0  0    0
                                                                     0 0  0    0
 7.719000+4 1.883290+2         -1          0          2          12864 1451    1
 0.000000+0 1.000000+0          0          0          0          62864 1451    2
 0.000000+0 0.000000+0          0          0          4        3112864 1451    3
 0.000000+0 0.000000+0          0          0         73          22864 1451    4
 77-Ir-190 HAR+WIN    EVAL-SEP98 A.L. NICHOLS                     2864 1451    5
                      DIST-NOV07 REV1-FEB03            261107     2864 1451    6
----JEFF-311          MATERIAL 2864         REVISION 1            2864 1451    7
-----RADIOACTIVE DECAY DATA                                       2864 1451    8
------ENDF-6 FORMAT                                               2864 1451    9
******************************************************************2864 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2864 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2864 1451   12
**             Original data taken from:  UKPADD67              **2864 1451   13
******************************************************************2864 1451   14
                                                                  2864 1451   15
          B SINGH                  NUCL DATA SHEETS 61(1990)243   2864 1451   16
          T C CHU                  PHYS REV 79(1950)582           2864 1451   17
          W R KANE ET AL           PHYS REV 119(1960)1953         2864 1451   18
          G R GANT, L YAFFE        CAN J CHEM 41(1963)2533        2864 1451   19
          B HARMATZ, T H HANDLEY   NUCL PHYS 56(1964)1            2864 1451   20
          T YAMAZAKI ET AL         NUCL PHYS A131(1969)169        2864 1451   21
          L SAMUELSSON ET AL       NUCL PHYS A135(1969)657        2864 1451   22
          P E HAUSTEIN, A F VOIGT  NUCL PHYS A136(1969)414        2864 1451   23
          S W YATES ET AL          NUCL PHYS A222(1974)276        2864 1451   24
          B P BAYHURST ET AL       PHYS REV 12C(1975)451          2864 1451   25
          P E GARRETT ET AL        NUCL PHYS A611(1996)68         2864 1451   26
                                                                  2864 1451   27
          N B GOVE, M J MARTIN     NUCL DATA TABLES 10(1971)205   2864 1451   28
                                                                  2864 1451   29
A comprehensive decay scheme has been derived from the gamma-ray  2864 1451   30
measurements of Harmatz and Handley, Yamazaki et al, Samuelsson   2864 1451   31
et al, Haustein and Voigt, and Yates et al, in which the studies  2864 1451   32
of Yates et al were particularly extensive.  When appropriate,    2864 1451   33
weighted mean data were calculated for the relative emission      2864 1451   34
probabilities of the gamma-ray transitions, although adjustments  2864 1451   35
have been made to the data derived for the 186.72, 361.13 and     2864 1451   36
447.9 keV gamma rays to maintain consistency.  EC decay to the    2864 1451   37
nuclear levels of Os-190 was calculated from these data and       2864 1451   38
theoretical internal conversion coefficients, assuming no direct  2864 1451   39
EC transitions to the 1203.9, 1050.4, 557.98, 547.85, 186.718 keV 2864 1451   40
and ground state nuclear levels of Os-190.  Small positron        2864 1451   41
emission probabilities to the 955.37 and 756.02 keV nuclear       2864 1451   42
levels of Os-190 were calculated from the theoretical tabulations 2864 1451   43
of Gove and Martin.                                               2864 1451   44
                                                                  2864 1451   45
Garrett et al have undertaken a detailed study of the long-lived  2864 1451   46
isomeric states of Ir-190, and identified the spin and parity of  2864 1451   47
the ground state to be 4- and the EC transitions to be either     2864 1451   48
allowed or first forbidden non-unique.                            2864 1451   49
                                                                  2864 1451   50
Further studies are merited to confirm the validity and detail of 2864 1451   51
the proposed decay scheme, and to re-assess the emission          2864 1451   52
probabilities of the 186.72 and 361.13 keV gamma-ray transitions. 2864 1451   53
                                                                  2864 1451   54
Feb 2003                                                          2864 1451   55
FIZCON reports 'FT value too small' for beta energy 1.125MeV      2864 1451   56
This has been reviewed and cannot be resolved at present.         2864 1451   57
                                                                  2864 1451   58
                                                                  2864 1451   59
      MEAN BETA+ ENERGIES:-                                       2864 1451   60
   END POINT(MEV)= 0.1030  SHAPE= 1  MEAN= 0.0582  INT= 0.0000    2864 1451   61
   END POINT(MEV)= 0.3020  SHAPE= 1  MEAN= 0.1552  INT= 0.0000    2864 1451   62
                                                                  2864 1451   63
      MEAN GAMMA ENERGY              =   1415.5381  KEV           2864 1451   64
      MAX. ANNIHILATION INTENSITY    =      0.0000                2864 1451   65
      MEAN BETA+ ENERGY              =      0.0001  KEV           2864 1451   66
      BETA+ + NEUTRINO ENERGY        =    592.1170  KEV           2864 1451   67
      MEAN X-RAY ENERGY              =     62.4798  KEV           2864 1451   68
      MEAN AUGER ELECTRON ENERGY     =     10.9601  KEV           2864 1451   69
      MEAN CONVERSION ELECTRON ENERGY=     61.1497  KEV           2864 1451   70
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.0635  KEV           2864 1451   71
      EFFECTIVE Q VALUE              =   2080.0000  KEV           2864 1451   72
      UNCERTAINTY IN EFFECTIVE Q (%) =      5.7692                2864 1451   73
      CALCULATED Q VALUE             =   2082.2100  KEV           2864 1451   74
      % DEVIATION                    =     -0.1063                2864 1451   75
                                                                  2864 1451   76
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2864 1451   77
                                1        451         79          12864 1451   78
                                8        457        500          12864 1451   79
 0.000000+0 0.000000+0          0          0          0          02864 1  099999
 0.000000+0 0.000000+0          0          0          0          02864 0  0    0
 7.719000+4 1.883290+2          0          0          0          42864 8457    1
 1.036800+6 1.728000+4          0          0          6          02864 8457    2
 7.210990+4 6.212410+3 1.478080+6 5.889670+4 0.000000+0 0.000000+02864 8457    3
 4.000000+0-1.000000+0          0          0          6          12864 8457    4
 2.000000+0 0.000000+0 2.080000+6 1.200000+5 1.000000+0 0.000000+02864 8457    5
 0.000000+0 0.000000+0          0          0          6         632864 8457    6
 4.892900-1 1.948500-2 1.415540+6 5.856440+4 0.000000+0 0.000000+02864 8457    7
 9.780000+4 2.000000+2          0          0         12          02864 8457    8
 2.000000+0 0.000000+0 1.939950-3 2.771360-4 0.000000+0 0.000000+02864 8457    9
 6.050000+0 5.989500-1 4.400000+0 4.356000-1 1.300000+0 1.287000-12864 8457   10
 1.867200+5 1.000000+1          0          0         12          02864 8457   11
 2.000000+0 0.000000+0 1.000000+0 9.237880-2 0.000000+0 0.000000+02864 8457   12
 4.250000-1 1.997500-2 2.050000-1 9.635000-3 1.630000-1 7.661000-32864 8457   13
 1.905000+5 1.000000+2          0          0         12          02864 8457   14
 2.000000+0 0.000000+0 2.725170-3 5.080830-4 0.000000+0 0.000000+02864 8457   15
 9.400000-1 1.974000-2 7.500000-1 1.575000-2 1.250000-1 2.625000-32864 8457   16
 1.969000+5 1.000000+2          0          0         12          02864 8457   17
 2.000000+0 0.000000+0 6.928410-2 6.928410-3 0.000000+0 0.000000+02864 8457   18
 6.110000-1 5.987800-2 4.330000-1 4.243400-2 1.220000-1 1.195600-22864 8457   19
 1.980000+5 1.000000+2          0          0         12          02864 8457   20
 2.000000+0 0.000000+0 3.926100-2 4.618940-3 0.000000+0 0.000000+02864 8457   21
 3.480000-1 1.009200-2 1.700000-1 4.930000-3 1.250000-1 3.625000-32864 8457   22
 1.994000+5 1.000000+2          0          0         12          02864 8457   23
 2.000000+0 0.000000+0 4.618940-3 1.385680-3 0.000000+0 0.000000+02864 8457   24
 3.400000-1 9.860000-3 1.650000-1 4.785000-3 1.230000-1 3.567000-32864 8457   25
 2.078000+5 1.000000+2          0          0         12          02864 8457   26
 2.000000+0 0.000000+0 6.928410-3 2.309470-3 0.000000+0 0.000000+02864 8457   27
 2.950000-1 5.015000-3 1.540000-1 2.618000-3 1.050000-1 1.785000-32864 8457   28
 2.082000+5 1.000000+2          0          0         12          02864 8457   29
 2.000000+0 0.000000+0 2.401850-2 3.233260-3 0.000000+0 0.000000+02864 8457   30
 2.900000-1 9.860000-3 1.520000-1 5.168000-3 1.030000-1 3.502000-32864 8457   31
 2.238000+5 1.000000+2          0          0         12          02864 8457   32
 2.000000+0 0.000000+0 7.575060-2 2.771360-3 0.000000+0 0.000000+02864 8457   33
 5.100000-2 1.989000-3 4.200000-2 1.638000-3 6.600000-3 2.574000-42864 8457   34
 2.356000+5 1.000000+2          0          0         12          02864 8457   35
 2.000000+0 0.000000+0 8.591220-3 6.466510-4 0.000000+0 0.000000+02864 8457   36
 4.450000-2 9.790000-4 3.700000-2 8.140000-4 5.900000-3 1.298000-42864 8457   37
 2.829000+5 1.000000+2          0          0         12          02864 8457   38
 2.000000+0 0.000000+0 9.699770-3 1.847580-3 0.000000+0 0.000000+02864 8457   39
 1.120000-1 5.040000-3 7.000000-2 3.150000-3 3.170000-2 1.426500-32864 8457   40
 2.883000+5 2.000000+2          0          0         12          02864 8457   41
 2.000000+0 0.000000+0 3.325640-2 2.771360-3 0.000000+0 0.000000+02864 8457   42
 1.390000-1 1.403900-2 9.900000-2 9.999000-3 3.100000-2 3.131000-32864 8457   43
 2.947000+5 1.000000+2          0          0         12          02864 8457   44
 2.000000+0 0.000000+0 1.247110-1 9.237880-3 0.000000+0 0.000000+02864 8457   45
 9.800000-2 4.998000-3 6.300000-2 3.213000-3 2.750000-2 1.402500-32864 8457   46
 3.611300+5 1.000000+1          0          0         12          02864 8457   47
 2.000000+0 0.000000+0 2.752890-1 1.385680-2 0.000000+0 0.000000+02864 8457   48
 5.400000-2 1.998000-3 3.700000-2 1.369000-3 1.250000-2 4.625000-42864 8457   49
 3.713000+5 1.000000+2          0          0         12          02864 8457   50
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 4.039290+5 2.019650+4          0          0          6          02864 8457  345
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 7.130000+4 1.426000+3          0          0          6          02864 8457  495
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 2.000000+0 0.000000+0 7.600000-7 7.600000-8 0.000000+0 0.000000+02864 8457  500
 0.000000+0 0.000000+0          0          0          0          02864 8  099999
 0.000000+0 0.000000+0          0          0          0          02864 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
 7.719000+4 1.883290+2         -1          0          2          12865 1451    1
 2.610000+4 1.000000+0          2          1          0          62865 1451    2
 0.000000+0 0.000000+0          0          0          4        3112865 1451    3
 0.000000+0 0.000000+0          0          0         43          22865 1451    4
 77-Ir-190MHAR+WIN    EVAL-SEP98 A.L. NICHOLS                     2865 1451    5
                      DIST-NOV07                       261107     2865 1451    6
----JEFF-311          MATERIAL 2865                               2865 1451    7
-----RADIOACTIVE DECAY DATA                                       2865 1451    8
------ENDF-6 FORMAT                                               2865 1451    9
******************************************************************2865 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2865 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2865 1451   12
**             Original data taken from:  UKPADD67              **2865 1451   13
******************************************************************2865 1451   14
                                                                  2865 1451   15
          B SINGH                   NUCL DATA SHEETS 61(1990)243  2865 1451   16
          B HARMATZ, T H HANDLEY    NUCL PHYS 56(1964)1           2865 1451   17
          P E GARRETT ET AL         NUCL PHYS A611(1996)68        2865 1451   18
                                                                  2865 1451   19
Decay-data studies of Ir-190m (half-life 1.120(3) hours) are      2865 1451   20
extremely sparse.  Only the gamma-ray measurements of Harmatz     2865 1451   21
and Handley, and Garrett et al have resulted in quantitative data 2865 1451   22
that can be used with any confidence to produce a recommended     2865 1451   23
decay scheme.  A simple isomeric transition has been proposed,    2865 1451   24
with a one gamma-ray decay to Ir-190 (26.1 keV gamma-ray          2865 1451   25
transition, M3 multipolarity). The emission probability was       2865 1451   26
calculated from the 100% transition probability and the           2865 1451   27
theoretical internal conversion coefficients, while an            2865 1451   28
uncertainty of 0.1 keV has been arbitrarily defined for the       2865 1451   29
Q-value and gamma-ray energy.  Furthermore, the  half-life of     2865 1451   30
1.120(3) hours has only been determined accurately by Garrett et  2865 1451   31
al.                                                               2865 1451   32
                                                                  2865 1451   33
Both the half-life and single gamma-ray transition need to be     2865 1451   34
re-determined to confirm the recommended values.                  2865 1451   35
                                                                  2865 1451   36
                                                                  2865 1451   37
      MEAN GAMMA ENERGY              =      0.0000  KEV           2865 1451   38
      MEAN X-RAY ENERGY              =      2.2831  KEV           2865 1451   39
      MEAN AUGER ELECTRON ENERGY     =      6.3111  KEV           2865 1451   40
      MEAN CONVERSION ELECTRON ENERGY=     17.5279  KEV           2865 1451   41
      EFFECTIVE Q VALUE              =     26.1000  KEV           2865 1451   42
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.3831                2865 1451   43
      CALCULATED Q VALUE             =     26.1222  KEV           2865 1451   44
      % DEVIATION                    =     -0.0849                2865 1451   45
                                                                  2865 1451   46
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2865 1451   47
                                1        451         49          12865 1451   48
                                8        457         26          12865 1451   49
 0.000000+0 0.000000+0          0          0          0          02865 1  099999
                                                                  2865 0  0    0
7.71900E+041.88329E+02          2          1          0          32865 8457    1
4.03200E+031.08000E+01          0          0          6          02865 8457    2
2.38390E+041.86295E+032.28316E+032.28313E+020.00000E+000.00000E+002865 8457    3
1.00000E+00-1.0000E+00          0          0          6          12865 8457    4
3.00000E+000.00000E+002.61000E+041.00000E+021.00000E+000.00000E+002865 8457    5
0.00000E+000.00000E+00          0          0          6          12865 8457    6
1.02000E-060.00000E+002.66220E-021.30898E-030.00000E+000.00000E+002865 8457    7
2.61000E+041.00000E+02          0          0         12          02865 8457    8
3.00000E+000.00000E+001.00000E+004.90196E-020.00000E+000.00000E+002865 8457    9
9.80000E+054.99800E+040.00000E+000.00000E+006.80000E+053.46800E+042865 8457   10
0.00000E+008.00000E+00          0          0          6          42865 8457   11
1.00000E+000.00000E+002.38390E+042.38390E+030.00000E+000.00000E+002865 8457   12
2.55800E+031.27900E+02          0          0          6          02865 8457   13
3.00000E+000.00000E+001.20392E+001.20392E-010.00000E+000.00000E+002865 8457   14
7.05900E+033.52950E+02          0          0          6          02865 8457   15
3.00000E+000.00000E+004.57776E-014.57776E-020.00000E+000.00000E+002865 8457   16
1.48848E+047.44240E+02          0          0          6          02865 8457   17
3.00000E+000.00000E+006.93600E-016.93600E-020.00000E+000.00000E+002865 8457   18
2.35420E+041.17710E+03          0          0          6          02865 8457   19
3.00000E+000.00000E+003.06000E-013.06000E-020.00000E+000.00000E+002865 8457   20
0.00000E+009.00000E+00          0          0          6          22865 8457   21
1.00000E+000.00000E+002.28313E+032.28313E+020.00000E+000.00000E+002865 8457   22
2.55800E+035.11600E+01          0          0          6          02865 8457   23
3.00000E+000.00000E+002.45698E-022.45698E-030.00000E+000.00000E+002865 8457   24
9.41500E+031.88300E+02          0          0          6          02865 8457   25
3.00000E+000.00000E+002.35824E-012.35824E-020.00000E+000.00000E+002865 8457   26
                                                                  2865 8  099999
                                                                  2865 0  0    0
                                                                     0 0  0    0
 7.719000+4 1.883290+2         -1          0          2          12866 1451    1
 3.764000+5 1.000000+0          6          2          0          62866 1451    2
 0.000000+0 0.000000+0          0          0          4        3112866 1451    3
 0.000000+0 0.000000+0          0          0         72          22866 1451    4
 77-Ir-190NHAR+WIN    EVAL-SEP98 A.L. NICHOLS                     2866 1451    5
                      DIST-NOV07                       261107     2866 1451    6
----JEFF-311          MATERIAL 2866                               2866 1451    7
-----RADIOACTIVE DECAY DATA                                       2866 1451    8
------ENDF-6 FORMAT                                               2866 1451    9
******************************************************************2866 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2866 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2866 1451   12
**             Original data taken from:  UKPADD67              **2866 1451   13
******************************************************************2866 1451   14
                                                                  2866 1451   15
          B SINGH                    NUCL DATA SHEETS 61(1990)243 2866 1451   16
          T C CHU                    PHYS REV 79(1950)582         2866 1451   17
          A H W ATEN ET AL           PHYSICA 21(1955)740          2866 1451   18
          A H W ATEN ET AL, ERRATUM  PHYSICA 21(1955)990          2866 1451   19
          G R GRANT, L YAFFE         CAN J CHEM 41(1963)2533      2866 1451   20
          B HARMATZ, T H HANDLEY     NUCL PHYS 56(1964)1          2866 1451   21
          M BORMANN ET AL            NUCL PHYS A157(1970)481      2866 1451   22
          P E GARRETT ET AL          NUCL PHYS A611(1996)68       2866 1451   23
                                                                  2866 1451   24
Ir-190n undergoes isomeric transition decay to Ir-190 (half-life  2866 1451   25
12.0(2) days) and EC decay to Os-190m (half-life 9.9(4)min).  The 2866 1451   26
proposed decay scheme is based on a combination of conversion-    2866 1451   27
electron and gamma-ray studies by Harmatz and Handley, and        2866 1451   28
Garrett et al.  Six gamma-ray transitions were identified with    2866 1451   29
the IT decay, while a cascade of five gamma rays were associated  2866 1451   30
with the subsequent decay of Os-190m (populated by the EC decay   2866 1451   31
of Ir-190n).  The studies of Garrett et al have resulted in       2866 1451   32
significant adjustments to the proposed decay scheme, including   2866 1451   33
the evolution of a nuclear level energy of 376.4(2) keV and spin/ 2866 1451   34
parity of 11- for Ir-190n.  Garrett et al also derived the IT and 2866 1451   35
EC branching fractions of 0.086(2) and 0.914(2), respectively.    2866 1451   36
The IT branching fraction of 0.086(2), the percentage split of    2866 1451   37
this transition probability at the 227.66 keV nuclear level       2866 1451   38
(83.5(7)% to 56.13 keV branch, and 16.5(7)% to 205.21 keV branch, 2866 1451   39
as determined by Garrett et al) and theoretical internal          2866 1451   40
conversion coefficients were used to calculate the relative       2866 1451   41
emission probabilities of the six gamma-ray transitions of the IT 2866 1451   42
decay (relative to 135.35 keV gamma ray (100%)); these resulting  2866 1451   43
data differed slightly from the equivalent measurements of        2866 1451   44
Garrett et al.                                                    2866 1451   45
                                                                  2866 1451   46
The EC decay mode is represented by a single EC transition to     2866 1451   47
Os-190m, while the IT decay mode populates the Ir-190 ground      2866 1451   48
state through the cascade of six gamma rays noted above.  This    2866 1451   49
latter decay does not involve the Ir-190m nuclear level, which    2866 1451   50
decays separately to the Ir-190 ground state.  Under these        2866 1451   51
circumstances, three data files have been assembled:  Ir-190n     2866 1451   52
decay to Ir-190 and Os-190m is contained within the Ir-190n data  2866 1451   53
file; the single gamma-ray transition of Ir-190m can be found in  2866 1451   54
the Ir-190m data file; five gamma-ray cascade from the Os-190m    2866 1451   55
nuclear level is contained with the Os-190m data file.            2866 1451   56
                                                                  2866 1451   57
The detailed studies of Garrett et al have resolved major         2866 1451   58
anomalies in the Ir-190n decay scheme.  Nevertheless, further     2866 1451   59
gamma-ray measurements are required to address specific           2866 1451   60
uncertainties in the relative emission probabilities of the       2866 1451   61
gamma rays leading to Ir-190.                                     2866 1451   62
                                                                  2866 1451   63
                                                                  2866 1451   64
      MEAN GAMMA ENERGY              =      8.5936  KEV           2866 1451   65
      BETA+ + NEUTRINO ENERGY        =    686.4140  KEV           2866 1451   66
      MEAN X-RAY ENERGY              =     50.2025  KEV           2866 1451   67
      MEAN AUGER ELECTRON ENERGY     =      9.4847  KEV           2866 1451   68
      MEAN CONVERSION ELECTRON ENERGY=     19.3938  KEV           2866 1451   69
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.0773  KEV           2866 1451   70
      EFFECTIVE Q VALUE              =    718.7844  KEV           2866 1451   71
      UNCERTAINTY IN EFFECTIVE Q (%) =     15.2609                2866 1451   72
      CALCULATED Q VALUE             =    718.1428  KEV           2866 1451   73
      % DEVIATION                    =      0.0893                2866 1451   74
                                                                  2866 1451   75
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2866 1451   76
                                1        451         78          12866 1451   77
                                8        457        100          12866 1451   78
 0.000000+0 0.000000+0          0          0          0          02866 1  099999
                                                                  2866 0  0    0
7.71900E+041.88329E+02          6          2          0          42866 8457    1
1.11132E+044.32000E+01          0          0          6          02866 8457    2
2.88785E+042.15889E+035.88734E+045.03186E+030.00000E+000.00000E+002866 8457    3
1.10000E+01-1.0000E+00          0          0         12          22866 8457    4
3.00000E+000.00000E+003.76400E+052.00000E+028.60000E-022.00000E-032866 8457    5
2.00000E+001.00000E+007.51000E+051.20000E+059.14000E-012.00000E-032866 8457    6
0.00000E+000.00000E+00          0          0          6          62866 8457    7
3.12000E-021.00000E-038.59358E+033.41565E+020.00000E+000.00000E+002866 8457    8
2.25000E+041.00000E+02          0          0         12          02866 8457    9
3.00000E+000.00000E+008.00000E-051.00000E-050.00000E+000.00000E+002866 8457   10
5.70000E+031.99500E+020.00000E+000.00000E+004.25000E+031.48750E+022866 8457   11
3.61800E+042.00000E+01          0          0         12          02866 8457   12
3.00000E+000.00000E+009.60000E-013.00000E-020.00000E+000.00000E+002866 8457   13
1.40000E+005.04000E-020.00000E+000.00000E+001.10000E+003.96000E-022866 8457   14
5.61300E+042.00000E+01          0          0         12          02866 8457   15
3.00000E+000.00000E+002.90000E-013.00000E-020.00000E+000.00000E+002866 8457   16
7.00000E+004.97000E-010.00000E+000.00000E+004.80000E+003.40800E-012866 8457   17
1.35350E+052.00000E+01          0          0         12          02866 8457   18
3.00000E+000.00000E+001.00000E+000.00000E+000.00000E+000.00000E+002866 8457   19
1.30000E+004.94000E-024.50000E-011.71000E-027.20000E-012.73600E-022866 8457   20
1.48700E+051.00000E+02          0          0         12          02866 8457   21
3.00000E+000.00000E+005.60000E-032.00000E-040.00000E+000.00000E+002866 8457   22
4.92000E+021.96800E+001.06000E+024.24000E-012.80000E+021.12000E+002866 8457   23
2.05210E+053.00000E+01          0          0         12          02866 8457   24
3.00000E+000.00000E+004.30000E-013.00000E-020.00000E+000.00000E+002866 8457   25
6.50000E-022.01500E-035.20000E-021.61200E-038.80000E-032.72800E-042866 8457   26
0.00000E+002.00000E+00          0          0          6          12866 8457   27
1.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002866 8457   28
7.51000E+051.20000E+05          0          0          6          02866 8457   29
2.00000E+001.00000E+009.14000E-012.00000E-030.00000E+000.00000E+002866 8457   30
0.00000E+008.00000E+00          0          0          6         212866 8457   31
1.00000E+000.00000E+002.88785E+042.88785E+030.00000E+000.00000E+002866 8457   32
2.45800E+031.22900E+02          0          0          6          02866 8457   33
2.00000E+000.00000E+001.13092E+001.13092E-010.00000E+000.00000E+002866 8457   34
2.55800E+031.27900E+02          0          0          6          02866 8457   35
3.00000E+000.00000E+003.01344E-013.01344E-020.00000E+000.00000E+002866 8457   36
6.88000E+033.44000E+02          0          0          6          02866 8457   37
2.00000E+000.00000E+004.96160E-014.96160E-020.00000E+000.00000E+002866 8457   38
7.05900E+033.52950E+02          0          0          6          02866 8457   39
3.00000E+000.00000E+001.22470E-011.22470E-020.00000E+000.00000E+002866 8457   40
1.12848E+045.64240E+02          0          0          6          02866 8457   41
3.00000E+000.00000E+001.06080E-021.06080E-030.00000E+000.00000E+002866 8457   42
1.99420E+049.97100E+02          0          0          6          02866 8457   43
3.00000E+000.00000E+003.61920E-033.61920E-040.00000E+000.00000E+002866 8457   44
2.49648E+041.24824E+03          0          0          6          02866 8457   45
3.00000E+000.00000E+003.29472E-023.29472E-030.00000E+000.00000E+002866 8457   46
3.36220E+041.68110E+03          0          0          6          02866 8457   47
3.00000E+000.00000E+008.98560E-038.98560E-040.00000E+000.00000E+002866 8457   48
4.49148E+042.24574E+03          0          0          6          02866 8457   49
3.00000E+000.00000E+004.34304E-024.34304E-030.00000E+000.00000E+002866 8457   50
5.35720E+042.67860E+03          0          0          6          02866 8457   51
3.00000E+000.00000E+001.99056E-021.99056E-030.00000E+000.00000E+002866 8457   52
5.42260E+042.71130E+03          0          0          6          02866 8457   53
2.00000E+000.00000E+002.92383E-022.92383E-030.00000E+000.00000E+002866 8457   54
5.58050E+042.79025E+03          0          0          6          02866 8457   55
3.00000E+000.00000E+001.26380E-031.26380E-040.00000E+000.00000E+002866 8457   56
5.92390E+042.96195E+03          0          0          6          02866 8457   57
3.00000E+000.00000E+001.40400E-021.40400E-030.00000E+000.00000E+002866 8457   58
7.25890E+043.62945E+03          0          0          6          02866 8457   59
3.00000E+000.00000E+001.85203E-021.85203E-030.00000E+000.00000E+002866 8457   60
1.24135E+056.20674E+03          0          0          6          02866 8457   61
3.00000E+000.00000E+002.24640E-022.24640E-030.00000E+000.00000E+002866 8457   62
1.29099E+056.45495E+03          0          0          6          02866 8457   63
3.00000E+000.00000E+006.97632E-046.97632E-050.00000E+000.00000E+002866 8457   64
1.32792E+056.63960E+03          0          0          6          02866 8457   65
3.00000E+000.00000E+004.05600E-034.05600E-040.00000E+000.00000E+002866 8457   66
1.37485E+056.87424E+03          0          0          6          02866 8457   67
3.00000E+000.00000E+004.89216E-024.89216E-030.00000E+000.00000E+002866 8457   68
1.46142E+057.30710E+03          0          0          6          02866 8457   69
3.00000E+000.00000E+001.85203E-021.85203E-030.00000E+000.00000E+002866 8457   70
1.93995E+059.69974E+03          0          0          6          02866 8457   71
3.00000E+000.00000E+001.18061E-041.18061E-050.00000E+000.00000E+002866 8457   72
2.02652E+051.01326E+04          0          0          6          02866 8457   73
3.00000E+000.00000E+005.63472E-055.63472E-060.00000E+000.00000E+002866 8457   74
0.00000E+009.00000E+00          0          0          6         122866 8457   75
1.00000E+000.00000E+005.02025E+045.02025E+030.00000E+000.00000E+002866 8457   76
2.45800E+034.91600E+01          0          0          6          02866 8457   77
2.00000E+000.00000E+002.13163E-022.13163E-030.00000E+000.00000E+002866 8457   78
2.55800E+035.11600E+01          0          0          6          02866 8457   79
3.00000E+000.00000E+006.14987E-036.14987E-040.00000E+000.00000E+002866 8457   80
9.13700E+031.82740E+02          0          0          6          02866 8457   81
2.00000E+000.00000E+002.41076E-012.41076E-020.00000E+000.00000E+002866 8457   82
9.41500E+031.88300E+02          0          0          6          02866 8457   83
3.00000E+000.00000E+006.30908E-026.30908E-030.00000E+000.00000E+002866 8457   84
6.14870E+041.22974E+03          0          0          6          02866 8457   85
2.00000E+000.00000E+002.02385E-012.02385E-020.00000E+000.00000E+002866 8457   86
6.30000E+041.26000E+03          0          0          6          02866 8457   87
2.00000E+000.00000E+003.48940E-013.48940E-020.00000E+000.00000E+002866 8457   88
6.32870E+041.26574E+03          0          0          6          02866 8457   89
3.00000E+000.00000E+009.22969E-039.22969E-040.00000E+000.00000E+002866 8457   90
6.48960E+041.29792E+03          0          0          6          02866 8457   91
3.00000E+000.00000E+001.58859E-021.58859E-030.00000E+000.00000E+002866 8457   92
7.13000E+041.42600E+03          0          0          6          02866 8457   93
2.00000E+000.00000E+001.20035E-011.20035E-020.00000E+000.00000E+002866 8457   94
7.34000E+041.46800E+03          0          0          6          02866 8457   95
2.00000E+000.00000E+003.03578E-023.03578E-030.00000E+000.00000E+002866 8457   96
7.35000E+041.47000E+03          0          0          6          02866 8457   97
3.00000E+000.00000E+005.46474E-035.46474E-040.00000E+000.00000E+002866 8457   98
7.56000E+041.51200E+03          0          0          6          02866 8457   99
3.00000E+000.00000E+001.41384E-031.41384E-040.00000E+000.00000E+002866 8457  100
                                                                  2866 8  099999
                                                                  2866 0  0    0
                                                                     0 0  0    0
 7.719100+4 1.893200+2         -1          0          2          12867 1451    1
 0.000000+0 0.000000+0          0          0          0          62867 1451    2
 0.000000+0 0.000000+0          0          0          4        3112867 1451    3
 0.000000+0 0.000000+0          0          0         22          22867 1451    4
 77-Ir-191 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2867 1451    5
                      DIST-NOV07                       261107     2867 1451    6
----JEFF-311          MATERIAL 2867                               2867 1451    7
-----RADIOACTIVE DECAY DATA                                       2867 1451    8
------ENDF-6 FORMAT                                               2867 1451    9
******************************************************************2867 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2867 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2867 1451   12
**             Original data taken from:  NUBASE                **2867 1451   13
******************************************************************2867 1451   14
******************************************************************2867 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2867 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2867 1451   17
                                                                  2867 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2867 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2867 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2867 1451   21
******************************************************************2867 1451   22
STABLE NUCLEUS                                                    2867 1451   23
       SPIN          1.5                                          2867 1451   24
       PARITY        1.0                                          2867 1451   25
NATURAL ABUNDANCE   37.3 2       %                                2867 1451   26
                                1        451         28          02867 1451   27
                                8        457          5          02867 1451   28
 0.000000+0 0.000000+0          0          0          0          02867 1  099999
                                                                  2867 0  0    0
 7.71910+04 1.89320+02          0          0          1          02867 8457    1
 0.00000+00 0.00000+00          0          0          6          02867 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002867 8457    3
 1.50000+00 1.00000+00          0          0          6          02867 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002867 8457    5
                                                                  2867 8  099999
                                                                  2867 0  0    0
                                                                     0 0  0    0
 7.719100+4 1.893200+2         -1          0          2          12868 1451    1
 1.712400+5 1.000000+0          3          1          0          62868 1451    2
 0.000000+0 0.000000+0          0          0          4        3112868 1451    3
 0.000000+0 0.000000+0          0          0         83          22868 1451    4
 77-Ir-191MHAR+WIN    EVAL-OCT00 A.L. NICHOLS                     2868 1451    5
                      DIST-NOV07 REV1-NOV05            261107     2868 1451    6
----JEFF-311          MATERIAL 2868         REVISION 1            2868 1451    7
-----RADIOACTIVE DECAY DATA                                       2868 1451    8
------ENDF-6 FORMAT                                               2868 1451    9
******************************************************************2868 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2868 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2868 1451   12
**             Original data taken from:  UKPADD67              **2868 1451   13
******************************************************************2868 1451   14
                                                                  2868 1451   15
     E Browne, S Y Chu         Nucl Data Sheets 74(1995)611       2868 1451   16
     E Browne                  Nucl Data Sheets 56(1989)709       2868 1451   17
     R A Naumann, J B Gerhart  Phys Rev 96(1954)1452 (T1/2)       2868 1451   18
     V K Fischer               Phys Rev 99(1955)764  (T1/2)       2868 1451   19
     E C Campbell, F Nelson    J Inorg Nucl Chem 3(1956)233       2868 1451   20
                               (T1/2)                             2868 1451   21
     J A R Cloutier, A Henrikson  Can J Phys 36(1958)1253         2868 1451   22
                                 (T1/2)                           2868 1451   23
     Z Plajner et al           Czech J Phys  B13(1963)23          2868 1451   24
                               (Egamma, Pce)                      2868 1451   25
     T Kaminishi, C Kojima     Japan J Appl Phys 2(1963)399       2868 1451   26
                               (T1/2)                             2868 1451   27
     J A Cameron et al         Phys Lett 10(1964)24 (delta)       2868 1451   28
     E P Mazets, Yu V Sergeenkov  Bull Acad Sci USSR, Phys Ser    2868 1451   29
                                  30(1967)1244 (Egamma, Pce)      2868 1451   30
     I Abrams                  Latv PSR Zinat Akad Vestis,        2868 1451   31
                               Fiz Teh Zinat Ser No. 5(1967)50    2868 1451   32
                               (T1/2)                             2868 1451   33
     A Lundan, A Siivola       Nucl Phys A106 (1968)417 (T1/2)    2868 1451   34
     S G Malmskog, A Backlin   Arkiv Fysik 39(1969)411            2868 1451   35
                               (Egamma, Pgamma)                   2868 1451   36
     W T K Johnson et al       Phys Rev Lett 25(1970)599 (T1/2)   2868 1451   37
     R H Price, M W Johns      Nucl Phys A174(1971) 497           2868 1451   38
                               (Egamma, spin/parity)              2868 1451   39
     W T K Johnson, C E Dick   Nucl Instrum Meth 99(1972)221      2868 1451   40
                               (T1/2)                             2868 1451   41
     K S Krane                 At Data Nucl Data Tables           2868 1451   42
                               18(1976)137 (delta)                2868 1451   43
     I Berkes et al            Hyperfine Interactions             2868 1451   44
                               15/16(1983)983 (delta)             2868 1451   45
     P T Prokof'ev et al       Bull Acad Sci USSR Phys Ser        2868 1451   46
                               51(1987)14 (Egamma, spin/parity)   2868 1451   47
     T Kibedi et al            Proc Int Conf Nucl Data for Sci    2868 1451   48
                               and Technol, 26 Sept - 1 Oct 2004, 2868 1451   49
                               Santa Fe, New Mexico, USA,         2868 1451   50
                               Editors: R C Haight et al,         2868 1451   51
                               AIP Conf Proc 769 (2005) Part 1,   2868 1451   52
                               268 (ICC)                          2868 1451   53
                                                                  2868 1451   54
The recommended half-life is the weighted-mean value of Fischer   2868 1451   55
(1955), Campbell and Nelson (1956), Cloutier and Henrikson        2868 1451   56
(1958), Kaminishi and Kojima (1963), Abrams (1967), Lundan and    2868 1451   57
Siivola (1968), and Johnson and Dick (1972).                      2868 1451   58
                                                                  2868 1451   59
A simple IT decay scheme has been derived primarily from the      2868 1451   60
conversion-electron and gamma-ray studies of Plajner et al        2868 1451   61
(1963), Mazets and Sergeenkov (1967), Malmskog and Backlin        2868 1451   62
(1969), Price and Johns (1971), and Prokof'ev et al (1987).       2868 1451   63
Decay from the 171.24-keV metastable state is assumed to occur    2868 1451   64
via a single E3 gamma-ray transition (41.83 keV) to the 129.415-  2868 1451   65
keV nuclear level of Ir-191.  The transition probabilities of the 2868 1451   66
47.00- and 129.415-keV gamma emissions from the 129.415-keV       2868 1451   67
nuclear level were assigned values of 0.36 and 99.64,             2868 1451   68
respectively.  A reasonably consistent decay scheme was           2868 1451   69
calculated from these data and ICCs derived from Kibedi et al,    2868 1451   70
with multipolarities of (56%M1 + 44%E2) and (86% + 14%E2) for the 2868 1451   71
82.42- and 129.415-keV gamma-ray transitions, respectively.       2868 1451   72
                                                                  2868 1451   73
Further studies are merited, particularly to confirm the absolute 2868 1451   74
emission probabilities of the 82.42- and 129.415-keV gamma rays.  2868 1451   75
                                                                  2868 1451   76
                                                                  2868 1451   77
      MEAN GAMMA ENERGY              =     34.4560  KEV           2868 1451   78
      MEAN X-RAY ENERGY              =     40.9297  KEV           2868 1451   79
      MEAN AUGER ELECTRON ENERGY     =     12.7357  KEV           2868 1451   80
      MEAN CONVERSION ELECTRON ENERGY=     82.9863  KEV           2868 1451   81
      EFFECTIVE Q VALUE              =    171.2400  KEV           2868 1451   82
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0292                2868 1451   83
      CALCULATED Q VALUE             =    171.1078  KEV           2868 1451   84
      % DEVIATION                    =      0.0772                2868 1451   85
                                                                  2868 1451   86
   ENDF-6  DATA PRODUCED BY COGEND (VERSION DATED - MAR 2004).    2868 1451   87
                                1        451         89          12868 1451   88
                                8        457         66          12868 1451   89
 0.000000+0 0.000000+0          0          0          0          02868 1  099999
 0.000000+0 0.000000+0          0          0          0          02868 0  0    0
 7.719100+4 1.893200+2          3          1          0          32868 8457    1
 4.900000+0 3.000000-2          0          0         34          02868 8457    2
 9.572200+4 8.395790+3 7.538570+4 4.842690+3 0.000000+0 0.000000+02868 8457    3
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.273570+4 1.273570+32868 8457    4
 8.298630+4 8.298630+3 3.445600+4 2.588300+3 4.092970+4 4.092970+32868 8457    5
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02868 8457    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02868 8457    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0                      2868 8457    8
 5.500000+0-1.000000+0          0          0          6          12868 8457    9
 3.000000+0 0.000000+0 1.712400+5 5.000000+1 1.000000+0 0.000000+02868 8457   10
 0.000000+0 0.000000+0          0          0          6          42868 8457   11
 2.660000-1 0.000000+0 3.445600+4 2.588300+3 0.000000+0 0.000000+02868 8457   12
 4.183000+4 6.000000+1          0          0         12          02868 8457   13
 3.000000+0 0.000000+0 2.206770-4 2.255640-6 0.000000+0 0.000000+02868 8457   14
 1.703000+4 3.406000+2 0.000000+0 0.000000+0 1.222000+4 2.444000+22868 8457   15
 4.700000+4 3.000000+1          0          0         12          02868 8457   16
 3.000000+0 0.000000+0 9.398500-5 7.518800-6 0.000000+0 0.000000+02868 8457   17
 1.442000+2 3.028200+0 0.000000+0 0.000000+0 1.087000+2 2.282700+02868 8457   18
 8.242000+4 1.200000+1          0          0         12          02868 8457   19
 3.000000+0 0.000000+0 1.278200-3 1.127820-4 0.000000+0 0.000000+02868 8457   20
 9.690000+0 9.690000-1 4.930000+0 4.930000-1 3.600000+0 3.600000-12868 8457   21
 1.294150+5 1.300000+1          0          0         12          02868 8457   22
 3.000000+0 0.000000+0 1.000000+0 7.518800-2 0.000000+0 0.000000+02868 8457   23
 2.750000+0 2.805000-1 2.150000+0 2.193000-1 4.600000-1 4.692000-22868 8457   24
 0.000000+0 8.000000+0          0          0          6         132868 8457   25
 1.000000+0 0.000000+0 9.572210+4 9.572210+3 0.000000+0 0.000000+02868 8457   26
 2.558000+3 1.279000+2          0          0          6          02868 8457   27
 3.000000+0 0.000000+0 2.116440+0 2.116440-1 0.000000+0 0.000000+02868 8457   28
 6.309000+3 3.154500+2          0          0          6          02868 8457   29
 3.000000+0 0.000000+0 1.676200-3 1.676200-4 0.000000+0 0.000000+02868 8457   30
 7.059000+3 3.529500+2          0          0          6          02868 8457   31
 3.000000+0 0.000000+0 8.649340-1 8.649340-2 0.000000+0 0.000000+02868 8457   32
 3.061480+4 1.530740+3          0          0          6          02868 8457   33
 3.000000+0 0.000000+0 7.173140-1 7.173140-2 0.000000+0 0.000000+02868 8457   34
 3.578480+4 1.789240+3          0          0          6          02868 8457   35
 3.000000+0 0.000000+0 2.717500-3 2.717500-4 0.000000+0 0.000000+02868 8457   36
 3.927200+4 1.963600+3          0          0          6          02868 8457   37
 3.000000+0 0.000000+0 2.823470-1 2.823470-2 0.000000+0 0.000000+02868 8457   38
 4.444200+4 2.222100+3          0          0          6          02868 8457   39
 3.000000+0 0.000000+0 8.875000-4 8.875000-5 0.000000+0 0.000000+02868 8457   40
 5.330400+4 2.665200+3          0          0          6          02868 8457   41
 3.000000+0 0.000000+0 5.719000-1 5.719000-2 0.000000+0 0.000000+02868 8457   42
 5.580500+4 2.790250+3          0          0          6          02868 8457   43
 3.000000+0 0.000000+0 2.179590-2 2.179590-3 0.000000+0 0.000000+02868 8457   44
 7.120480+4 3.560240+3          0          0          6          02868 8457   45
 3.000000+0 0.000000+0 1.224000-3 1.224000-4 0.000000+0 0.000000+02868 8457   46
 7.986200+4 3.993100+3          0          0          6          02868 8457   47
 3.000000+0 0.000000+0 3.944000-4 3.944000-5 0.000000+0 0.000000+02868 8457   48
 1.182000+5 5.909990+3          0          0          6          02868 8457   49
 3.000000+0 0.000000+0 1.223600-1 1.223600-2 0.000000+0 0.000000+02868 8457   50
 1.268570+5 6.342850+3          0          0          6          02868 8457   51
 3.000000+0 0.000000+0 3.724000-2 3.724000-3 0.000000+0 0.000000+02868 8457   52
 0.000000+0 9.000000+0          0          0          6          62868 8457   53
 1.000000+0 0.000000+0 4.092970+4 4.092970+3 0.000000+0 0.000000+02868 8457   54
 2.558000+3 5.116000+1          0          0          6          02868 8457   55
 3.000000+0 0.000000+0 4.319260-2 4.319260-3 0.000000+0 0.000000+02868 8457   56
 9.415000+3 1.883000+2          0          0          6          02868 8457   57
 3.000000+0 0.000000+0 4.455720-1 4.455720-2 0.000000+0 0.000000+02868 8457   58
 6.328700+4 1.265740+3          0          0          6          02868 8457   59
 3.000000+0 0.000000+0 1.591780-1 1.591780-2 0.000000+0 0.000000+02868 8457   60
 6.489600+4 1.297920+3          0          0          6          02868 8457   61
 3.000000+0 0.000000+0 2.739720-1 2.739720-2 0.000000+0 0.000000+02868 8457   62
 7.350000+4 1.470000+3          0          0          6          02868 8457   63
 3.000000+0 0.000000+0 9.424650-2 9.424650-3 0.000000+0 0.000000+02868 8457   64
 7.560000+4 1.512000+3          0          0          6          02868 8457   65
 3.000000+0 0.000000+0 2.438350-2 2.438350-3 0.000000+0 0.000000+02868 8457   66
 0.000000+0 0.000000+0          0          0          0          02868 8  099999
 0.000000+0 0.000000+0          0          0          0          02868 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
 7.719100+4 1.893200+2         -1          0          2          12869 1451    1
 2.085000+6 1.000000+0         69          2          0          62869 1451    2
 0.000000+0 0.000000+0          0          0          4        3112869 1451    3
 0.000000+0 0.000000+0          0          0         45          22869 1451    4
 77-Ir-191NHAR+WIN    EVAL-OCT00 A.L. NICHOLS                     2869 1451    5
                      DIST-NOV07                       261107     2869 1451    6
----JEFF-311          MATERIAL 2869                               2869 1451    7
-----RADIOACTIVE DECAY DATA                                       2869 1451    8
------ENDF-6 FORMAT                                               2869 1451    9
******************************************************************2869 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2869 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2869 1451   12
**             Original data taken from:  UKPADD67              **2869 1451   13
******************************************************************2869 1451   14
                                                                  2869 1451   15
          E BROWNE             NUCL DATA SHEETS 56(1989)709       2869 1451   16
          E BROWNE, S Y CHU    NUCL DATA SHEETS 74(1995)611       2869 1451   17
          J LUKASIAK ET AL     NUCL PHYS A313(1979)191            2869 1451   18
                                                                  2869 1451   19
 Ir-191n has been observed and partially characterised by Lukasiak2869 1451   20
et al.  There are large uncertainties in the gamma-ray decay to   2869 1451   21
the first isomeric state (Ir-191m):  a number of significant      2869 1451   22
assumption were made on the basis of a simple gamma-ray cascade   2869 1451   23
of E2 transitions from a nuclear level of 2085(40) keV (which is  2869 1451   24
the mid-point of the energy range proposed by Lukasiak et al      2869 1451   25
(2047 to 2123 keV)).  The spin and parity were also derived from  2869 1451   26
the four gamma-ray cascade (all E2 transitions), and the known    2869 1451   27
spins and parities of the lower nuclear levels.  Thus, the simple 2869 1451   28
decay scheme and gamma-ray emission probabilities were calculated 2869 1451   29
from a series of 100% transition probabilities and theoretical    2869 1451   30
internal conversion coefficients.                                 2869 1451   31
                                                                  2869 1451   32
 Lukasiak et al detected Ir-191n in their analysis of the levels  2869 1451   33
of Ir-191 excited via the Os-192(p, 2n) and Os-192(d, 3n) nuclear 2869 1451   34
reactions.  Further studies are required to resolve a number of   2869 1451   35
issues, including the fundamental need to confirm the existence   2869 1451   36
of this isomeric state.                                           2869 1451   37
                                                                  2869 1451   38
                                                                  2869 1451   39
      MEAN GAMMA ENERGY              =   1862.6472  KEV           2869 1451   40
      MEAN X-RAY ENERGY              =      5.4026  KEV           2869 1451   41
      MEAN AUGER ELECTRON ENERGY     =      0.9249  KEV           2869 1451   42
      MEAN CONVERSION ELECTRON ENERGY=     44.8387  KEV           2869 1451   43
      EFFECTIVE Q VALUE              =   1914.0000  KEV           2869 1451   44
      UNCERTAINTY IN EFFECTIVE Q (%) =      2.0899                2869 1451   45
      CALCULATED Q VALUE             =   1913.8135  KEV           2869 1451   46
      % DEVIATION                    =      0.0097                2869 1451   47
                                                                  2869 1451   48
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2869 1451   49
                                1        451         51          12869 1451   50
                                8        457         65          12869 1451   51
 0.000000+0 0.000000+0          0          0          0          02869 1  099999
                                                                  2869 0  0    0
7.71910E+041.89320E+02         69          2          0          32869 8457    1
5.50000E+007.00000E-01          0          0          6          02869 8457    2
4.57636E+044.48482E+031.86805E+063.87324E+040.00000E+000.00000E+002869 8457    3
1.35000E+01-1.0000E+00          0          0          6          12869 8457    4
3.00000E+001.00000E+001.91400E+064.00000E+041.00000E+000.00000E+002869 8457    5
0.00000E+000.00000E+00          0          0          6          42869 8457    6
9.80000E-010.00000E+001.86265E+063.87286E+040.00000E+000.00000E+002869 8457    7
4.20200E+052.00000E+02          0          0         12          02869 8457    8
3.00000E+000.00000E+009.83674E-011.02041E-030.00000E+000.00000E+002869 8457    9
3.73000E-027.08700E-042.65000E-025.03500E-048.20000E-031.55800E-042869 8457   10
4.33000E+054.00000E+04          0          0         12          02869 8457   11
3.00000E+000.00000E+009.86735E-011.02041E-030.00000E+000.00000E+002869 8457   12
3.45000E-026.90000E-042.47000E-024.94000E-047.40000E-031.48000E-042869 8457   13
5.24600E+051.60000E+03          0          0         12          02869 8457   14
3.00000E+000.00000E+009.98980E-011.02041E-030.00000E+000.00000E+002869 8457   15
2.14000E-024.06600E-041.60000E-023.04000E-044.10000E-037.79000E-052869 8457   16
5.36000E+056.00000E+02          0          0         12          02869 8457   17
3.00000E+000.00000E+001.00000E+001.02041E-030.00000E+000.00000E+002869 8457   18
2.03000E-024.06000E-041.53000E-023.06000E-043.80000E-037.60000E-052869 8457   19
0.00000E+008.00000E+00          0          0          6         152869 8457   20
1.00000E+000.00000E+004.57636E+044.57636E+030.00000E+000.00000E+002869 8457   21
2.55800E+031.27900E+02          0          0          6          02869 8457   22
3.00000E+000.00000E+001.34925E-011.34925E-020.00000E+000.00000E+002869 8457   23
7.05900E+033.52950E+02          0          0          6          02869 8457   24
3.00000E+000.00000E+005.80740E-025.80740E-030.00000E+000.00000E+002869 8457   25
5.58050E+042.79025E+03          0          0          6          02869 8457   26
3.00000E+000.00000E+003.04338E-033.04338E-040.00000E+000.00000E+002869 8457   27
3.44089E+051.72045E+04          0          0          6          02869 8457   28
3.00000E+000.00000E+002.55460E-022.55460E-030.00000E+000.00000E+002869 8457   29
3.56889E+051.78445E+04          0          0          6          02869 8457   30
3.00000E+000.00000E+002.38849E-022.38849E-030.00000E+000.00000E+002869 8457   31
4.08985E+052.04492E+04          0          0          6          02869 8457   32
3.00000E+000.00000E+007.90480E-037.90480E-040.00000E+000.00000E+002869 8457   33
4.17642E+052.08821E+04          0          0          6          02869 8457   34
3.00000E+000.00000E+002.50640E-032.50640E-040.00000E+000.00000E+002869 8457   35
4.21785E+052.10892E+04          0          0          6          02869 8457   36
3.00000E+000.00000E+007.15580E-037.15580E-040.00000E+000.00000E+002869 8457   37
4.30442E+052.15221E+04          0          0          6          02869 8457   38
3.00000E+000.00000E+002.32080E-032.32080E-040.00000E+000.00000E+002869 8457   39
4.48489E+052.24245E+04          0          0          6          02869 8457   40
3.00000E+000.00000E+001.56640E-021.56640E-030.00000E+000.00000E+002869 8457   41
4.59889E+052.29945E+04          0          0          6          02869 8457   42
3.00000E+000.00000E+001.49940E-021.49940E-030.00000E+000.00000E+002869 8457   43
5.13385E+052.56692E+04          0          0          6          02869 8457   44
3.00000E+000.00000E+004.01390E-034.01390E-040.00000E+000.00000E+002869 8457   45
5.22042E+052.61021E+04          0          0          6          02869 8457   46
3.00000E+000.00000E+001.27270E-031.27270E-040.00000E+000.00000E+002869 8457   47
5.24785E+052.62392E+04          0          0          6          02869 8457   48
3.00000E+000.00000E+003.72400E-033.72400E-040.00000E+000.00000E+002869 8457   49
5.33442E+052.66721E+04          0          0          6          02869 8457   50
3.00000E+000.00000E+001.17600E-031.17600E-040.00000E+000.00000E+002869 8457   51
0.00000E+009.00000E+00          0          0          6          62869 8457   52
1.00000E+000.00000E+005.40257E+035.40257E+020.00000E+000.00000E+002869 8457   53
2.55800E+035.11600E+01          0          0          6          02869 8457   54
3.00000E+000.00000E+002.75357E-032.75357E-040.00000E+000.00000E+002869 8457   55
9.41500E+031.88300E+02          0          0          6          02869 8457   56
3.00000E+000.00000E+002.99169E-022.99169E-030.00000E+000.00000E+002869 8457   57
6.32870E+041.26574E+03          0          0          6          02869 8457   58
3.00000E+000.00000E+002.22261E-022.22261E-030.00000E+000.00000E+002869 8457   59
6.48960E+041.29792E+03          0          0          6          02869 8457   60
3.00000E+000.00000E+003.82550E-023.82550E-030.00000E+000.00000E+002869 8457   61
7.35000E+041.47000E+03          0          0          6          02869 8457   62
3.00000E+000.00000E+001.31597E-021.31597E-030.00000E+000.00000E+002869 8457   63
7.56000E+041.51200E+03          0          0          6          02869 8457   64
3.00000E+000.00000E+003.40469E-033.40469E-040.00000E+000.00000E+002869 8457   65
                                                                  2869 8  099999
                                                                  2869 0  0    0
                                                                     0 0  0    0
 7.719200+4 1.903140+2         -1          0          2          12870 1451    1
 0.000000+0 1.000000+0          0          0          0          62870 1451    2
 0.000000+0 0.000000+0          0          0          4        3112870 1451    3
 0.000000+0 0.000000+0          0          0        116          22870 1451    4
 77-Ir-192 HAR+WIN    EVAL-SEP03 A.L. NICHOLS                     2870 1451    5
                      DIST-NOV07                       261107     2870 1451    6
----JEFF-311          MATERIAL 2870                               2870 1451    7
-----RADIOACTIVE DECAY DATA                                       2870 1451    8
------ENDF-6 FORMAT                                               2870 1451    9
******************************************************************2870 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2870 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2870 1451   12
**             Original data taken from:  UKPADD67              **2870 1451   13
******************************************************************2870 1451   14
                                                                  2870 1451   15
     C M Baglin           Nucl Data Sheets 84(1998)717            2870 1451   16
     J Kastner            Can J Phys 29(1951)480 (T1/2)           2870 1451   17
     J W Allison          Brit J Appl Phys 11(1960)302 (T1/2)     2870 1451   18
     E I Wyatt et al      Nucl Sci Eng 11(1961)74 (T1/2)          2870 1451   19
     G Harbottle          Nucl Phys 41(1963)604 (T1/2)            2870 1451   20
     W M Doyle, R Marrus  Nucl Phys 49(1963)449 (spin)            2870 1451   21
     M W Johns, M Kawamura  Nucl Phys 61(1965)385 (Ebeta, Pbeta)  2870 1451   22
     S L Lee              PhD thesis, Univ Michigan(1969)         2870 1451   23
                                         (Egamma, Pgamma)         2870 1451   24
     J B Willett          Nucl Instrum Meth  84(1970)157          2870 1451   25
                                           (Pgamma, ICC)          2870 1451   26
     F Lagoutine et al    Int J Appl Radiat Isot  23(1972)219     2870 1451   27
                                                        (T1/2)    2870 1451   28
     R J Gehrke           Nucl Phys A204(1973)26 (Egamma, Pgamma) 2870 1451   29
     N A Voinova et al    Nucl Phys A235(1974)123 (ICC)           2870 1451   30
     R Prasad et al       Nucl Phys A243(1975)317 (Egamma, Pgamma)2870 1451   31
     F Rosel et al        At Data Nucl Data Tables 21(1978)92     2870 1451   32
                                                        (ICC)     2870 1451   33
     V Hnatowicz          Nucl Instrum Meth 161(1979)151          2870 1451   34
     H Houtermans et al   Int J Appl Radiat Isot 31(1980)153      2870 1451   35
                                                       (T1/2)     2870 1451   36
     Y Yoshizawa et al    Nucl Instrum Meth 174(1980)133          2870 1451   37
     U Schotzig           Nucl Instrum Meth 206(1983)441          2870 1451   38
                                        (Egamma, Pgamma)          2870 1451   39
     H H Hansen, D Mouchel  Int J Appl Radiat Isot 34(1983)1233   2870 1451   40
                                                           (ICC)  2870 1451   41
     Y Iwata et al        Nucl Instrum Meth Phys Res              2870 1451   42
                          219(1984)123  (Egamma, Pgamma)          2870 1451   43
     E Eid, N M Stewart   Z Phys  A320(1985)495  (Egamma, Pgamma) 2870 1451   44
     V N Danilenko et al  pp.529 in Proc 35th Ann Conf Nucl       2870 1451   45
                          Spectrosc Struct At Nuclei, Leningrad   2870 1451   46
                          (1985) (Pgamma)                         2870 1451   47
     D Mehta et al        Nucl Instrum Meth Phys Res              2870 1451   48
                          A245(1986)447  (Egamma, Pgamma)         2870 1451   49
     D Mehta et al        Z Phys  A328(1987)31  (Egamma, Pgamma)  2870 1451   50
     Y Liu et al          Z Phys  A329(1988)307  (Egamma, Pgamma) 2870 1451   51
     K Singh, K S Dhillon Pramana  39(1992)571  (Egamma, Pgamma)  2870 1451   52
     M J Woods et al      Nucl Instrum Meth Phys Res A312(1992)3462870 1451   53
                                                            (T1/2)2870 1451   54
     M P Unterweger et al Nucl Instrum Meth Phys Res A312(1992)3492870 1451   55
                                                            (T1/2)2870 1451   56
     O Helene, V R Vanin  Nucl Instrum Meth Phys Res A335(1993)2272870 1451   57
     H Miyahara et al     Nucl Instrum Meth Phys Res A339(1994)2032870 1451   58
                                                  (Egamma, Pgamma)2870 1451   59
     R G Helmer, C van der Leun  Nucl Instrum Meth Phys Res       2870 1451   60
                                 A450(2000)35  (Egamma)           2870 1451   61
     M J Woods            IAEA-TECDOC(2003), in preparation (T1/2)2870 1451   62
     E Browne             IAEA-TECDOC(2003), in preparation       2870 1451   63
                          (decay scheme, Pbeta, PEC, Pgamma)      2870 1451   64
                                                                  2870 1451   65
Recommended half-life of 73.822(9) days is the weighted average   2870 1451   66
of the measurements of Houtermans et al, Woods et al (1992),      2870 1451   67
and Unterweger et al, as specified by Woods (2003); uncertainty   2870 1451   68
of the measured value of Houtermans et al was increased by        2870 1451   69
~ 62% to ensure a weighting factor not greater than 0.50.         2870 1451   70
                                                                  2870 1451   71
Gamma-ray energies were adopted from Helmer and van der Leun      2870 1451   72
(for 205.79430, 295.95650, 308.45507, 316.50618, 416.4688,        2870 1451   73
468.06885, 484.5751, 588.5810, 604.41105, 612.46215 and           2870 1451   74
884.5365-keV gamma rays).  Gamma-ray emission probabilities       2870 1451   75
were derived from the experimental measurements of Gehrke,        2870 1451   76
Schotzig, Iwata et al, Eid and Stewart, Danilenko et al, Mehta    2870 1451   77
et al (1986), Mehta et al (1987), Liu et al, Singh and Dhillon,   2870 1451   78
and Miyahara et al, as proposed by Browne (2003).  Gamma-         2870 1451   79
transition multipolarities and mixing ratios were adopted from    2870 1451   80
various studies (see also Browne (2003)).  Direct beta decay to   2870 1451   81
the 612.46, 316.06-keV nuclear levels and ground state of Pt-     2870 1451   82
192, and direct EC decay to the 489.06, 205.79-keV nuclear        2870 1451   83
levels and ground state of Os-192 were assumed to be zero from    2870 1451   84
spin and parity considerations.  Therefore, on the basis of no    2870 1451   85
direct beta and EC transitions to the ground states of Pt-192     2870 1451   86
and Os-192 respectively, the gamma-ray transition probabilities   2870 1451   87
to these ground states can be summed to normalise the decay       2870 1451   88
scheme of Ir-192.  These decay data, Q-values and the internal    2870 1451   89
conversion coefficients of Rosel et al were also used to          2870 1451   90
determine B- and EC decay branches to individual nuclear levels,  2870 1451   91
and the overall beta and EC branching fractions.                  2870 1451   92
                                                                  2870 1451   93
The good consistency of the measured decay data and evaluated     2870 1451   94
decay scheme indicate that these data are both complete and of    2870 1451   95
good quality.                                                     2870 1451   96
                                                                  2870 1451   97
                                                                  2870 1451   98
      MEAN BETA- ENERGIES:-                                       2870 1451   99
   END POINT(MEV)= 0.0535  SHAPE= 0  MEAN= 0.0137  INT= 0.0000    2870 1451  100
   END POINT(MEV)= 0.0757  SHAPE= 1  MEAN= 0.0195  INT= 0.0000    2870 1451  101
   END POINT(MEV)= 0.0817  SHAPE= 1  MEAN= 0.0211  INT= 0.0010    2870 1451  102
   END POINT(MEV)= 0.2587  SHAPE= 0  MEAN= 0.0716  INT= 0.0559    2870 1451  103
   END POINT(MEV)= 0.5388  SHAPE= 0  MEAN= 0.1619  INT= 0.4140    2870 1451  104
   END POINT(MEV)= 0.6751  SHAPE= 0  MEAN= 0.2096  INT= 0.4790    2870 1451  105
                                                                  2870 1451  106
      MEAN GAMMA ENERGY              =    806.8878  KEV           2870 1451  107
      MEAN BETA- ENERGY              =    171.4670  KEV           2870 1451  108
      BETA- + NEUTRINO ENERGY        =    560.9860  KEV           2870 1451  109
      BETA+ + NEUTRINO ENERGY        =     17.4511  KEV           2870 1451  110
      MEAN X-RAY ENERGY              =      9.5936  KEV           2870 1451  111
      MEAN AUGER ELECTRON ENERGY     =      1.7579  KEV           2870 1451  112
      MEAN CONVERSION ELECTRON ENERGY=     44.0616  KEV           2870 1451  113
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.0010  KEV           2870 1451  114
      EFFECTIVE Q VALUE              =   1439.8521  KEV           2870 1451  115
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.1772                2870 1451  116
      CALCULATED Q VALUE             =   1437.9471  KEV           2870 1451  117
      % DEVIATION                    =      0.1323                2870 1451  118
                                                                  2870 1451  119
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2870 1451  120
                                1        451        122          12870 1451  121
                                8        457        318          12870 1451  122
 0.000000+0 0.000000+0          0          0          0          02870 1  099999
 0.000000+0 0.000000+0          0          0          0          02870 0  0    0
 7.719200+4 1.903140+2          0          0          0          52870 8457    1
 6.378220+6 7.776000+2          0          0         34          02870 8457    2
 2.172870+5 4.495470+3 8.164820+5 1.834410+3 0.000000+0 0.000000+02870 8457    3
 1.714670+5 8.741310+2 0.000000+0 0.000000+0 1.757890+3 1.757890+22870 8457    4
 4.406160+4 4.406160+3 8.068880+5 1.563550+3 9.593620+3 9.593620+22870 8457    5
 9.798820-1 9.798820-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02870 8457    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02870 8457    7
 0.000000+0 0.000000+0 4.069700+5 1.991230+3                      2870 8457    8
 4.000000+0 1.000000+0          0          0         12          22870 8457    9
 1.000000+0 0.000000+0 1.459700+6 1.900000+3 9.520000-1 1.000000-32870 8457   10
 2.000000+0 0.000000+0 1.046200+6 2.300000+3 4.800000-2 1.000000-32870 8457   11
 0.000000+0 0.000000+0          0          0          6         272870 8457   12
 8.275000-1 0.000000+0 8.068880+5 1.563550+3 0.000000+0 0.000000+02870 8457   13
 1.104000+5 3.000000+2          0          0         12          02870 8457   14
 2.000000+0 0.000000+0 1.474320-4 1.329310-5 0.000000+0 0.000000+02870 8457   15
 3.650000+0 1.095000-1 2.030000+0 6.090000-2 1.220000+0 3.660000-22870 8457   16
 1.363430+5 3.000000-1          0          0         12          02870 8457   17
 1.000000+0 0.000000+0 2.404830-3 3.021150-4 0.000000+0 0.000000+02870 8457   18
 1.560000+0 5.928000-2 5.700000-1 2.166000-2 7.470000-1 2.838600-22870 8457   19
 1.769800+5 4.000000+1          0          0         12          02870 8457   20
 1.000000+0 0.000000+0 5.196370-5 1.450150-5 0.000000+0 0.000000+02870 8457   21
 9.700000-2 3.007000-3 7.860000-2 2.436600-3 1.370000-2 4.247000-42870 8457   22
 2.013110+5 7.000000-1          0          0         12          02870 8457   23
 2.000000+0 0.000000+0 5.716010-3 9.667670-5 0.000000+0 0.000000+02870 8457   24
 3.870000-1 1.006200-2 2.280000-1 5.928000-3 1.200000-1 3.120000-32870 8457   25
 2.057940+5 9.000000-2          0          0         12          02870 8457   26
 2.000000+0 0.000000+0 4.036250-2 4.833840-4 0.000000+0 0.000000+02870 8457   27
 3.050000-1 9.150000-3 1.570000-1 4.710000-3 1.110000-1 3.330000-32870 8457   28
 2.802700+5 2.400000+2          0          0         12          02870 8457   29
 1.000000+0 0.000000+0 1.087610-4 6.042300-5 0.000000+0 0.000000+02870 8457   30
 1.600000-1 1.600000-2 1.100000-1 1.100000-2 3.900000-2 3.900000-32870 8457   31
 2.832670+5 8.000000-1          0          0         12          02870 8457   32
 2.000000+0 0.000000+0 3.214500-3 3.625380-5 0.000000+0 0.000000+02870 8457   33
 1.230000-1 4.059000-3 8.100000-2 2.673000-3 3.180000-2 1.049400-32870 8457   34
 2.959560+5 1.500000-1          0          0         12          02870 8457   35
 1.000000+0 0.000000+0 3.470690-1 1.691840-3 0.000000+0 0.000000+02870 8457   36
 1.060000-1 2.968000-3 6.540000-2 1.831200-3 3.050000-2 8.540000-42870 8457   37
 3.084550+5 1.700000-1          0          0         12          02870 8457   38
 1.000000+0 0.000000+0 3.586710-1 1.812690-3 0.000000+0 0.000000+02870 8457   39
 9.600000-2 2.976000-3 6.080000-2 1.884800-3 2.620000-2 8.122000-42870 8457   40
 3.165060+5 1.700000-1          0          0         12          02870 8457   41
 1.000000+0 0.000000+0 1.000000+0 2.537760-3 0.000000+0 0.000000+02870 8457   42
 8.490000-2 2.462100-3 5.370000-2 1.557300-3 2.360000-2 6.844000-42870 8457   43
 3.291700+5 1.500000+2          0          0         12          02870 8457   44
 2.000000+0 0.000000+0 2.102720-4 2.054380-5 0.000000+0 0.000000+02870 8457   45
 9.400000-2 6.956000-3 6.900000-2 5.106000-3 1.950000-2 1.443000-32870 8457   46
 3.744850+5 8.000000-1          0          0         12          02870 8457   47
 2.000000+0 0.000000+0 8.773410-3 7.250760-5 0.000000+0 0.000000+02870 8457   48
 4.900000-2 1.519000-3 3.410000-2 1.057100-3 1.130000-2 3.503000-42870 8457   49
 4.164690+5 7.000000-1          0          0         12          02870 8457   50
 1.000000+0 0.000000+0 8.084590-3 2.537760-4 0.000000+0 0.000000+02870 8457   51
 5.000000-2 4.000000-3 3.700000-2 2.960000-3 9.900000-3 7.920000-42870 8457   52
 4.205200+5 6.000000+1          0          0         12          02870 8457   53
 2.000000+0 0.000000+0 8.338370-4 8.459210-5 0.000000+0 0.000000+02870 8457   54
 3.580000-2 1.109800-3 2.580000-2 7.998000-4 7.610000-3 2.359100-42870 8457   55
 4.680690+5 2.600000-1          0          0         12          02870 8457   56
 1.000000+0 0.000000+0 5.777640-1 2.900300-3 0.000000+0 0.000000+02870 8457   57
 2.950000-2 9.145000-4 2.130000-2 6.603000-4 6.170000-3 1.912700-42870 8457   58
 4.845750+5 4.000000-1          0          0         12          02870 8457   59
 2.000000+0 0.000000+0 3.853780-2 2.900300-4 0.000000+0 0.000000+02870 8457   60
 2.630000-2 7.890000-4 1.980000-2 5.940000-4 4.990000-3 1.497000-42870 8457   61
 4.890600+5 3.000000+1          0          0         12          02870 8457   62
 2.000000+0 0.000000+0 5.293050-3 1.691840-4 0.000000+0 0.000000+02870 8457   63
 2.430000-2 7.047000-4 1.820000-2 5.278000-4 4.710000-3 1.365900-42870 8457   64
 5.885810+5 7.000000-1          0          0         12          02870 8457   65
 1.000000+0 0.000000+0 5.458610-2 2.658610-4 0.000000+0 0.000000+02870 8457   66
 1.700000-2 4.930000-4 1.290000-2 3.741000-4 3.110000-3 9.019000-52870 8457   67
 5.934900+5 1.300000+2          0          0         12          02870 8457   68
 1.000000+0 0.000000+0 5.087610-4 2.054380-5 0.000000+0 0.000000+02870 8457   69
 6.700000-3 4.020000-4 5.500000-3 3.300000-4 8.700000-4 5.220000-52870 8457   70
 5.994100+5 1.500000+2          0          0         12          02870 8457   71
 1.000000+0 0.000000+0 4.712990-5 2.054380-5 0.000000+0 0.000000+02870 8457   72
 5.900000-3 1.829000-4 4.810000-3 1.491100-4 7.520000-4 2.331200-52870 8457   73
 6.044110+5 2.500000-1          0          0         12          02870 8457   74
 1.000000+0 0.000000+0 9.909370-2 4.833840-4 0.000000+0 0.000000+02870 8457   75
 2.660000-2 7.980000-4 2.130000-2 6.390000-4 4.030000-3 1.209000-42870 8457   76
 6.124620+5 2.600000-1          0          0         12          02870 8457   77
 1.000000+0 0.000000+0 6.453170-2 9.667670-4 0.000000+0 0.000000+02870 8457   78
 1.550000-2 4.960000-4 1.190000-2 3.808000-4 2.780000-3 8.896000-52870 8457   79
 7.658000+5 3.000000+2          0          0         12          02870 8457   80
 1.000000+0 0.000000+0 1.571000-5 7.250760-6 0.000000+0 0.000000+02870 8457   81
 5.200000-3 4.992000-4 4.300000-3 4.128000-4 7.000000-4 6.720000-52870 8457   82
 8.845360+5 7.000000-1          0          0         12          02870 8457   83
 1.000000+0 0.000000+0 3.516620-3 8.459210-5 0.000000+0 0.000000+02870 8457   84
 7.070000-3 2.121000-4 5.660000-3 1.698000-4 1.080000-3 3.240000-52870 8457   85
 1.061480+6 4.000000+1          0          0         12          02870 8457   86
 1.000000+0 0.000000+0 6.404830-4 1.208460-5 0.000000+0 0.000000+02870 8457   87
 1.970000-3 9.062000-5 1.660000-3 7.636000-5 2.430000-4 1.117800-52870 8457   88
 1.089900+6 3.000000+2          0          0         12          02870 8457   89
 1.000000+0 0.000000+0 1.450150-5 2.416920-6 0.000000+0 0.000000+02870 8457   90
 6.300000-3 5.985000-4 5.200000-3 4.940000-4 8.700000-4 8.265000-52870 8457   91
 1.378200+6 1.500000+2          0          0         12          02870 8457   92
 1.000000+0 0.000000+0 1.450150-5 3.625380-6 0.000000+0 0.000000+02870 8457   93
 6.200000-3 1.922000-4 4.920000-3 1.525200-4 9.800000-4 3.038000-52870 8457   94
 0.000000+0 1.000000+0          0          0          6          62870 8457   95
 1.000000+0 0.000000+0 1.714670+5 8.741310+2 0.000000+0 0.000000+02870 8457   96
 5.350000+4 1.900000+3          0          0          6          02870 8457   97
 1.000000+0 1.000000+0 3.300000-5 5.000000-6 0.000000+0 0.000000+02870 8457   98
 7.570000+4 1.900000+3          0          0          6          02870 8457   99
 1.000000+0 1.000000+0 3.900000-5 1.700000-5 0.000000+0 0.000000+02870 8457  100
 8.170000+4 1.900000+3          0          0          6          02870 8457  101
 1.000000+0 1.000000+0 1.026000-3 2.300000-5 0.000000+0 0.000000+02870 8457  102
 2.587000+5 1.900000+3          0          0          6          02870 8457  103
 1.000000+0 1.000000+0 5.590000-2 3.000000-4 0.000000+0 0.000000+02870 8457  104
 5.388000+5 1.900000+3          0          0          6          02870 8457  105
 1.000000+0 1.000000+0 4.140000-1 3.000000-3 0.000000+0 0.000000+02870 8457  106
 6.751000+5 1.900000+3          0          0          6          02870 8457  107
 1.000000+0 1.000000+0 4.790000-1 3.000000-3 0.000000+0 0.000000+02870 8457  108
 0.000000+0 2.000000+0          0          0          6          32870 8457  109
 1.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02870 8457  110
 1.366000+5 2.300000+3          0          0          6          02870 8457  111
 2.000000+0 1.000000+0 9.500000-4 4.000000-5 0.000000+0 0.000000+02870 8457  112
 3.558000+5 2.300000+3          0          0          6          02870 8457  113
 2.000000+0 1.000000+0 3.970000-2 3.000000-4 0.000000+0 0.000000+02870 8457  114
 4.659000+5 2.300000+3          0          0          6          02870 8457  115
 2.000000+0 1.000000+0 6.860000-3 9.000000-5 0.000000+0 0.000000+02870 8457  116
 0.000000+0 8.000000+0          0          0          6         872870 8457  117
 1.000000+0 0.000000+0 4.581950+4 4.581950+3 0.000000+0 0.000000+02870 8457  118
 2.458000+3 1.229000+2          0          0          6          02870 8457  119
 2.000000+0 0.000000+0 7.623980-2 7.623980-3 0.000000+0 0.000000+02870 8457  120
 2.658000+3 1.329000+2          0          0          6          02870 8457  121
 1.000000+0 0.000000+0 1.825480-1 1.825480-2 0.000000+0 0.000000+02870 8457  122
 6.880000+3 3.440000+2          0          0          6          02870 8457  123
 2.000000+0 0.000000+0 3.321750-2 3.321750-3 0.000000+0 0.000000+02870 8457  124
 7.240000+3 3.620000+2          0          0          6          02870 8457  125
 1.000000+0 0.000000+0 7.705970-2 7.705970-3 0.000000+0 0.000000+02870 8457  126
 3.652920+4 1.826460+3          0          0          6          02870 8457  127
 2.000000+0 0.000000+0 2.476600-4 2.476600-5 0.000000+0 0.000000+02870 8457  128
 5.422600+4 2.711300+3          0          0          6          02870 8457  129
 2.000000+0 0.000000+0 1.756600-3 1.756600-4 0.000000+0 0.000000+02870 8457  130
 5.741700+4 2.870850+3          0          0          6          02870 8457  131
 1.000000+0 0.000000+0 3.545660-3 3.545660-4 0.000000+0 0.000000+02870 8457  132
 5.794780+4 2.897390+3          0          0          6          02870 8457  133
 1.000000+0 0.000000+0 1.134300-3 1.134300-4 0.000000+0 0.000000+02870 8457  134
 9.858520+4 4.929260+3          0          0          6          02870 8457  135
 1.000000+0 0.000000+0 3.379800-6 3.379800-7 0.000000+0 0.000000+02870 8457  136
 9.952910+4 4.976460+3          0          0          6          02870 8457  137
 2.000000+0 0.000000+0 1.488400-4 1.488400-5 0.000000+0 0.000000+02870 8457  138
 1.079420+5 5.397100+3          0          0          6          02870 8457  139
 2.000000+0 0.000000+0 4.880000-5 4.880000-6 0.000000+0 0.000000+02870 8457  140
 1.247790+5 6.238950+3          0          0          6          02870 8457  141
 1.000000+0 0.000000+0 1.486530-3 1.486530-4 0.000000+0 0.000000+02870 8457  142
 1.274400+5 6.372020+3          0          0          6          02870 8457  143
 2.000000+0 0.000000+0 1.078440-3 1.078440-4 0.000000+0 0.000000+02870 8457  144
 1.319240+5 6.596180+3          0          0          6          02870 8457  145
 2.000000+0 0.000000+0 5.243800-3 5.243800-4 0.000000+0 0.000000+02870 8457  146
 1.336850+5 6.684230+3          0          0          6          02870 8457  147
 1.000000+0 0.000000+0 4.835700-4 4.835700-5 0.000000+0 0.000000+02870 8457  148
 1.654160+5 8.270820+3          0          0          6          02870 8457  149
 1.000000+0 0.000000+0 5.891000-7 5.891000-8 0.000000+0 0.000000+02870 8457  150
 1.743220+5 8.716100+3          0          0          6          02870 8457  151
 1.000000+0 0.000000+0 2.021000-7 2.021000-8 0.000000+0 0.000000+02870 8457  152
 1.904400+5 9.522010+3          0          0          6          02870 8457  153
 2.000000+0 0.000000+0 5.676000-4 5.676000-5 0.000000+0 0.000000+02870 8457  154
 1.949230+5 9.746170+3          0          0          6          02870 8457  155
 2.000000+0 0.000000+0 3.707400-3 3.707400-4 0.000000+0 0.000000+02870 8457  156
 1.988530+5 9.942660+3          0          0          6          02870 8457  157
 2.000000+0 0.000000+0 1.844700-4 1.844700-5 0.000000+0 0.000000+02870 8457  158
 2.018750+5 1.009380+4          0          0          6          02870 8457  159
 1.000000+0 0.000000+0 9.900000-6 9.900000-7 0.000000+0 0.000000+02870 8457  160
 2.033360+5 1.016680+4          0          0          6          02870 8457  161
 2.000000+0 0.000000+0 1.235800-3 1.235800-4 0.000000+0 0.000000+02870 8457  162
 2.093960+5 1.046980+4          0          0          6          02870 8457  163
 2.000000+0 0.000000+0 2.154600-4 2.154600-5 0.000000+0 0.000000+02870 8457  164
 2.175620+5 1.087810+4          0          0          6          02870 8457  165
 1.000000+0 0.000000+0 1.878290-2 1.878290-3 0.000000+0 0.000000+02870 8457  166
 2.300600+5 1.150300+4          0          0          6          02870 8457  167
 1.000000+0 0.000000+0 1.804540-2 1.804540-3 0.000000+0 0.000000+02870 8457  168
 2.381110+5 1.190560+4          0          0          6          02870 8457  169
 1.000000+0 0.000000+0 4.443670-2 4.443670-3 0.000000+0 0.000000+02870 8457  170
 2.552990+5 1.276500+4          0          0          6          02870 8457  171
 2.000000+0 0.000000+0 1.200600-5 1.200600-6 0.000000+0 0.000000+02870 8457  172
 2.687060+5 1.343530+4          0          0          6          02870 8457  173
 1.000000+0 0.000000+0 3.510000-6 3.510000-7 0.000000+0 0.000000+02870 8457  174
 2.723960+5 1.361980+4          0          0          6          02870 8457  175
 2.000000+0 0.000000+0 8.458800-5 8.458800-6 0.000000+0 0.000000+02870 8457  176
 2.776120+5 1.388060+4          0          0          6          02870 8457  177
 1.000000+0 0.000000+0 9.900000-7 9.900000-8 0.000000+0 0.000000+02870 8457  178
 2.808090+5 1.404040+4          0          0          6          02870 8457  179
 2.000000+0 0.000000+0 2.713200-5 2.713200-6 0.000000+0 0.000000+02870 8457  180
 2.843930+5 1.421960+4          0          0          6          02870 8457  181
 1.000000+0 0.000000+0 8.759600-3 8.759600-4 0.000000+0 0.000000+02870 8457  182
 2.932980+5 1.466490+4          0          0          6          02870 8457  183
 1.000000+0 0.000000+0 2.900720-3 2.900720-4 0.000000+0 0.000000+02870 8457  184
 2.968910+5 1.484460+4          0          0          6          02870 8457  185
 1.000000+0 0.000000+0 7.776160-3 7.776160-4 0.000000+0 0.000000+02870 8457  186
 3.006140+5 1.503070+4          0          0          6          02870 8457  187
 2.000000+0 0.000000+0 2.475660-4 2.475660-5 0.000000+0 0.000000+02870 8457  188
 3.049420+5 1.524710+4          0          0          6          02870 8457  189
 1.000000+0 0.000000+0 1.952900-2 1.952900-3 0.000000+0 0.000000+02870 8457  190
 3.057970+5 1.528990+4          0          0          6          02870 8457  191
 1.000000+0 0.000000+0 2.671200-3 2.671200-4 0.000000+0 0.000000+02870 8457  192
 3.138480+5 1.569240+4          0          0          6          02870 8457  193
 1.000000+0 0.000000+0 6.289000-3 6.289000-4 0.000000+0 0.000000+02870 8457  194
 3.182990+5 1.591500+4          0          0          6          02870 8457  195
 2.000000+0 0.000000+0 3.393000-6 3.393000-7 0.000000+0 0.000000+02870 8457  196
 3.267120+5 1.633560+4          0          0          6          02870 8457  197
 2.000000+0 0.000000+0 9.570000-7 9.570000-8 0.000000+0 0.000000+02870 8457  198
 3.380740+5 1.690370+4          0          0          6          02870 8457  199
 1.000000+0 0.000000+0 2.475300-4 2.475300-5 0.000000+0 0.000000+02870 8457  200
 3.466490+5 1.733250+4          0          0          6          02870 8457  201
 2.000000+0 0.000000+0 1.780200-5 1.780200-6 0.000000+0 0.000000+02870 8457  202
 3.636140+5 1.818070+4          0          0          6          02870 8457  203
 2.000000+0 0.000000+0 8.203800-5 8.203800-6 0.000000+0 0.000000+02870 8457  204
 3.720270+5 1.860140+4          0          0          6          02870 8457  205
 2.000000+0 0.000000+0 2.613600-5 2.613600-6 0.000000+0 0.000000+02870 8457  206
 3.896740+5 1.948370+4          0          0          6          02870 8457  207
 1.000000+0 0.000000+0 1.018350-2 1.018350-3 0.000000+0 0.000000+02870 8457  208
 4.049050+5 2.024530+4          0          0          6          02870 8457  209
 1.000000+0 0.000000+0 6.623100-5 6.623100-6 0.000000+0 0.000000+02870 8457  210
 4.096490+5 2.048250+4          0          0          6          02870 8457  211
 2.000000+0 0.000000+0 5.250900-6 5.250900-7 0.000000+0 0.000000+02870 8457  212
 4.107040+5 2.053520+4          0          0          6          02870 8457  213
 2.000000+0 0.000000+0 6.314220-4 6.314220-5 0.000000+0 0.000000+02870 8457  214
 4.138110+5 2.069050+4          0          0          6          02870 8457  215
 1.000000+0 0.000000+0 2.073900-5 2.073900-6 0.000000+0 0.000000+02870 8457  216
 4.151890+5 2.075950+4          0          0          6          02870 8457  217
 2.000000+0 0.000000+0 7.971600-5 7.971600-6 0.000000+0 0.000000+02870 8457  218
 4.180620+5 2.090310+4          0          0          6          02870 8457  219
 2.000000+0 0.000000+0 1.649100-6 1.649100-7 0.000000+0 0.000000+02870 8457  220
 4.565050+5 2.282530+4          0          0          6          02870 8457  221
 1.000000+0 0.000000+0 2.949880-3 2.949880-4 0.000000+0 0.000000+02870 8457  222
 4.654110+5 2.327050+4          0          0          6          02870 8457  223
 1.000000+0 0.000000+0 9.705430-4 9.705430-5 0.000000+0 0.000000+02870 8457  224
 4.737040+5 2.368520+4          0          0          6          02870 8457  225
 2.000000+0 0.000000+0 1.591310-4 1.591310-5 0.000000+0 0.000000+02870 8457  226
 4.781890+5 2.390950+4          0          0          6          02870 8457  227
 2.000000+0 0.000000+0 2.062980-5 2.062980-6 0.000000+0 0.000000+02870 8457  228
 4.821170+5 2.410590+4          0          0          6          02870 8457  229
 2.000000+0 0.000000+0 4.815390-5 4.815390-6 0.000000+0 0.000000+02870 8457  230
 4.866020+5 2.433010+4          0          0          6          02870 8457  231
 2.000000+0 0.000000+0 6.088200-6 6.088200-7 0.000000+0 0.000000+02870 8457  232
 5.101860+5 2.550930+4          0          0          6          02870 8457  233
 1.000000+0 0.000000+0 5.826930-4 5.826930-5 0.000000+0 0.000000+02870 8457  234
 5.150950+5 2.575480+4          0          0          6          02870 8457  235
 1.000000+0 0.000000+0 2.315500-6 2.315500-7 0.000000+0 0.000000+02870 8457  236
 5.210150+5 2.605080+4          0          0          6          02870 8457  237
 1.000000+0 0.000000+0 1.875900-7 1.875900-8 0.000000+0 0.000000+02870 8457  238
 5.260160+5 2.630080+4          0          0          6          02870 8457  239
 1.000000+0 0.000000+0 1.746600-3 1.746600-4 0.000000+0 0.000000+02870 8457  240
 5.340670+5 2.670340+4          0          0          6          02870 8457  241
 1.000000+0 0.000000+0 6.354600-4 6.354600-5 0.000000+0 0.000000+02870 8457  242
 5.770170+5 2.885090+4          0          0          6          02870 8457  243
 1.000000+0 0.000000+0 1.404790-4 1.404790-5 0.000000+0 0.000000+02870 8457  244
 5.819260+5 2.909630+4          0          0          6          02870 8457  245
 1.000000+0 0.000000+0 3.662700-7 3.662700-8 0.000000+0 0.000000+02870 8457  246
 5.859230+5 2.929620+4          0          0          6          02870 8457  247
 1.000000+0 0.000000+0 4.471830-5 4.471830-6 0.000000+0 0.000000+02870 8457  248
 5.878460+5 2.939230+4          0          0          6          02870 8457  249
 1.000000+0 0.000000+0 2.932800-8 2.932800-9 0.000000+0 0.000000+02870 8457  250
 5.908320+5 2.954160+4          0          0          6          02870 8457  251
 1.000000+0 0.000000+0 1.389300-7 1.389300-8 0.000000+0 0.000000+02870 8457  252
 5.928470+5 2.964240+4          0          0          6          02870 8457  253
 1.000000+0 0.000000+0 3.304600-4 3.304600-5 0.000000+0 0.000000+02870 8457  254
 5.967520+5 2.983760+4          0          0          6          02870 8457  255
 1.000000+0 0.000000+0 1.318200-8 1.318200-9 0.000000+0 0.000000+02870 8457  256
 6.008980+5 3.004490+4          0          0          6          02870 8457  257
 1.000000+0 0.000000+0 1.484520-4 1.484520-5 0.000000+0 0.000000+02870 8457  258
 6.017530+5 3.008770+4          0          0          6          02870 8457  259
 1.000000+0 0.000000+0 1.041400-4 1.041400-5 0.000000+0 0.000000+02870 8457  260
 6.098040+5 3.049020+4          0          0          6          02870 8457  261
 1.000000+0 0.000000+0 4.378800-5 4.378800-6 0.000000+0 0.000000+02870 8457  262
 6.874050+5 3.437030+4          0          0          6          02870 8457  263
 1.000000+0 0.000000+0 5.590000-8 5.590000-9 0.000000+0 0.000000+02870 8457  264
 7.542360+5 3.771180+4          0          0          6          02870 8457  265
 1.000000+0 0.000000+0 9.100000-9 9.10000-10 0.000000+0 0.000000+02870 8457  266
 7.631420+5 3.815710+4          0          0          6          02870 8457  267
 1.000000+0 0.000000+0 2.600000-9 2.60000-10 0.000000+0 0.000000+02870 8457  268
 8.061420+5 4.030710+4          0          0          6          02870 8457  269
 1.000000+0 0.000000+0 1.647060-5 1.647060-6 0.000000+0 0.000000+02870 8457  270
 8.729730+5 4.364860+4          0          0          6          02870 8457  271
 1.000000+0 0.000000+0 3.142800-6 3.142800-7 0.000000+0 0.000000+02870 8457  272
 8.818780+5 4.409390+4          0          0          6          02870 8457  273
 1.000000+0 0.000000+0 9.603000-7 9.603000-8 0.000000+0 0.000000+02870 8457  274
 9.830850+5 4.915430+4          0          0          6          02870 8457  275
 1.000000+0 0.000000+0 8.798000-7 8.798000-8 0.000000+0 0.000000+02870 8457  276
 1.011510+6 5.057530+4          0          0          6          02870 8457  277
 1.000000+0 0.000000+0 6.240000-8 6.240000-9 0.000000+0 0.000000+02870 8457  278
 1.049920+6 5.249580+4          0          0          6          02870 8457  279
 1.000000+0 0.000000+0 1.287900-7 1.287900-8 0.000000+0 0.000000+02870 8457  280
 1.058820+6 5.294110+4          0          0          6          02870 8457  281
 1.000000+0 0.000000+0 3.551000-8 3.551000-9 0.000000+0 0.000000+02870 8457  282
 1.078340+6 5.391680+4          0          0          6          02870 8457  283
 1.000000+0 0.000000+0 1.044000-8 1.044000-9 0.000000+0 0.000000+02870 8457  284
 1.087240+6 5.436210+4          0          0          6          02870 8457  285
 1.000000+0 0.000000+0 2.760000-9 2.76000-10 0.000000+0 0.000000+02870 8457  286
 1.299810+6 6.499030+4          0          0          6          02870 8457  287
 1.000000+0 0.000000+0 5.904000-8 5.904000-9 0.000000+0 0.000000+02870 8457  288
 1.366640+6 6.833180+4          0          0          6          02870 8457  289
 1.000000+0 0.000000+0 1.176000-8 1.176000-9 0.000000+0 0.000000+02870 8457  290
 1.375540+6 6.877710+4          0          0          6          02870 8457  291
 1.000000+0 0.000000+0 3.600000-9 3.60000-10 0.000000+0 0.000000+02870 8457  292
 0.000000+0 9.000000+0          0          0          6         122870 8457  293
 1.000000+0 0.000000+0 9.593610+3 9.593610+2 0.000000+0 0.000000+02870 8457  294
 2.458000+3 4.916000+1          0          0          6          02870 8457  295
 2.000000+0 0.000000+0 1.437020-3 1.437020-4 0.000000+0 0.000000+02870 8457  296
 2.658000+3 5.316000+1          0          0          6          02870 8457  297
 1.000000+0 0.000000+0 4.201880-3 4.201880-4 0.000000+0 0.000000+02870 8457  298
 9.137000+3 1.827400+2          0          0          6          02870 8457  299
 2.000000+0 0.000000+0 1.613980-2 1.613980-3 0.000000+0 0.000000+02870 8457  300
 9.695000+3 1.939000+2          0          0          6          02870 8457  301
 1.000000+0 0.000000+0 4.204340-2 4.204340-3 0.000000+0 0.000000+02870 8457  302
 6.148700+4 1.229740+3          0          0          6          02870 8457  303
 2.000000+0 0.000000+0 1.215910-2 1.215910-3 0.000000+0 0.000000+02870 8457  304
 6.300000+4 1.260000+3          0          0          6          02870 8457  305
 2.000000+0 0.000000+0 2.096390-2 2.096390-3 0.000000+0 0.000000+02870 8457  306
 6.512200+4 1.302440+3          0          0          6          02870 8457  307
 1.000000+0 0.000000+0 2.666050-2 2.666050-3 0.000000+0 0.000000+02870 8457  308
 6.683200+4 1.336640+3          0          0          6          02870 8457  309
 1.000000+0 0.000000+0 4.572980-2 4.572990-3 0.000000+0 0.000000+02870 8457  310
 7.130000+4 1.426000+3          0          0          6          02870 8457  311
 2.000000+0 0.000000+0 7.211600-3 7.211600-4 0.000000+0 0.000000+02870 8457  312
 7.340000+4 1.468000+3          0          0          6          02870 8457  313
 2.000000+0 0.000000+0 1.823860-3 1.823860-4 0.000000+0 0.000000+02870 8457  314
 7.570000+4 1.514000+3          0          0          6          02870 8457  315
 1.000000+0 0.000000+0 1.573110-2 1.573110-3 0.000000+0 0.000000+02870 8457  316
 7.790000+4 1.558000+3          0          0          6          02870 8457  317
 1.000000+0 0.000000+0 4.161420-3 4.161420-4 0.000000+0 0.000000+02870 8457  318
 0.000000+0 0.000000+0          0          0          0          02870 8  099999
 0.000000+0 0.000000+0          0          0          0          02870 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
 7.719200+4 1.903140+2         -1          0          2          12871 1451    1
 5.672000+4 1.000000+0          3          1          0          62871 1451    2
 0.000000+0 0.000000+0          0          0          4        3112871 1451    3
 0.000000+0 0.000000+0          0          0         73          22871 1451    4
 77-Ir-192MHAR+WIN    EVAL-SEP03 A.L. NICHOLS                     2871 1451    5
                      DIST-NOV07                       261107     2871 1451    6
----JEFF-311          MATERIAL 2871                               2871 1451    7
-----RADIOACTIVE DECAY DATA                                       2871 1451    8
------ENDF-6 FORMAT                                               2871 1451    9
******************************************************************2871 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2871 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2871 1451   12
**             Original data taken from:  UKPADD67              **2871 1451   13
******************************************************************2871 1451   14
                                                                  2871 1451   15
    C M Baglin                   Nucl Data Sheets 84(1998)717     2871 1451   16
    G Weber, A Flammersfeld      Z Naturforsch 8A(1953)580        2871 1451   17
    G Weber                      Z Naturforsch 9A(1954)115 (T1/2) 2871 1451   18
    J P Mize et al               Phys Rev 96(1954)444             2871 1451   19
    G Scharff-Goldhaber, M McKeown  Phys Rev Letts 3(1959)47      2871 1451   20
                                                     (Pbeta)      2871 1451   21
    G Scharff-Goldhaber, M McKeown  Naturwissenschaften           2871 1451   22
                                    48(1961)96 (T1/2)             2871 1451   23
    H-H Hennies, A Flammersfeld  Naturwissenschaften 48(1961)97   2871 1451   24
    B Keisch                     J Inorg Nucl Chem 25(1963)220    2871 1451   25
                                                         (ICC)    2871 1451   26
    R J Gehrke, R A Lokken       Nucl Instrum Meth 97(1971)219    2871 1451   27
    F Rosel et al                At Data Nucl Data Tables         2871 1451   28
                                 21(1978)92 (ICC)                 2871 1451   29
    R G Helmer, C van der Leun   Nucl Instrum Meth Phys Res       2871 1451   30
                                 A450(2000)35 (Egamma)            2871 1451   31
    E Browne                     IAEA-TECDOC (2003),              2871 1451   32
                                 in preparation                   2871 1451   33
                                                                  2871 1451   34
The recommended half-life of 1.44(7) mins is the average of the   2871 1451   35
measurements of Weber (1954), and Scharff-Goldhaber and McKeown   2871 1451   36
(1961).                                                           2871 1451   37
                                                                  2871 1451   38
The low-intensity gamma-ray emission probabilities were derived   2871 1451   39
from measurements of the beta population of the 612.46, 316.06    2871 1451   40
and 0.0-keV nuclear levels of Pt-192 by Scharff-Goldhaber and     2871 1451   41
McKeown (1959).  Uncertainties for these three beta transitions   2871 1451   42
were arbitrarily defined as ~ 10%.  Gamma-transition              2871 1451   43
multipolarities and mixing ratios were adopted from various       2871 1451   44
studies (see also Browne (2003)), while gamma-ray energies were   2871 1451   45
taken from Helmer and van der Leun (2000).  These decay data,     2871 1451   46
Q-values and the internal conversion coefficients of Rosel et     2871 1451   47
al were used to determine the gamma-ray emission probabilities,   2871 1451   48
and the overall beta and IT branching fractions.  Thus, the       2871 1451   49
transition probability of the single IT gamma ray (56.720(5)      2871 1451   50
keV, E2) was defined as 0.999825(18), and this parameter was      2871 1451   51
used in conjunction with the total internal conversion            2871 1451   52
coefficient to calculate the absolute emission probability of     2871 1451   53
0.0342(7).                                                        2871 1451   54
                                                                  2871 1451   55
Further studies are merited to confirm the full validity of the   2871 1451   56
proposed decay scheme.                                            2871 1451   57
                                                                  2871 1451   58
                                                                  2871 1451   59
      MEAN BETA- ENERGIES:-                                       2871 1451   60
   END POINT(MEV)= 0.9039  SHAPE= 1  MEAN= 0.2938  INT= 0.0000    2871 1451   61
   END POINT(MEV)= 1.2003  SHAPE= 1  MEAN= 0.4086  INT= 0.0001    2871 1451   62
   END POINT(MEV)= 1.5164  SHAPE= 1  MEAN= 0.5363  INT= 0.0001    2871 1451   63
                                                                  2871 1451   64
      MEAN GAMMA ENERGY              =      0.0569  KEV           2871 1451   65
      MEAN BETA- ENERGY              =      0.0774  KEV           2871 1451   66
      BETA- + NEUTRINO ENERGY        =      0.2248  KEV           2871 1451   67
      MEAN X-RAY ENERGY              =      2.3814  KEV           2871 1451   68
      MEAN AUGER ELECTRON ENERGY     =      6.4782  KEV           2871 1451   69
      MEAN CONVERSION ELECTRON ENERGY=     47.8786  KEV           2871 1451   70
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.0002  KEV           2871 1451   71
      EFFECTIVE Q VALUE              =     56.9754  KEV           2871 1451   72
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0487                2871 1451   73
      CALCULATED Q VALUE             =     57.0199  KEV           2871 1451   74
      % DEVIATION                    =     -0.0780                2871 1451   75
                                                                  2871 1451   76
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2871 1451   77
                                1        451         79          12871 1451   78
                                8        457         85          12871 1451   79
 0.000000+0 0.000000+0          0          0          0          02871 1  099999
 0.000000+0 0.000000+0          0          0          0          02871 0  0    0
 7.719200+4 1.903140+2          3          1          0          42871 8457    1
 8.640000+1 4.200000+0          0          0         34          02871 8457    2
 5.443420+4 4.831490+3 2.438510+3 2.381770+2 0.000000+0 0.000000+02871 8457    3
 7.742600+1 6.740740+0 0.000000+0 0.000000+0 6.478170+3 6.478170+22871 8457    4
 4.787860+4 4.787860+3 5.690630+1 3.912610+0 2.381450+3 2.381450+22871 8457    5
 1.532980-1 1.532980-2 0.000000+0 0.000000+0 0.000000+0 0.000000+02871 8457    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02871 8457    7
 0.000000+0 0.000000+0 1.473430+2 1.278910+1                      2871 8457    8
 1.000000+0-1.000000+0          0          0         12          22871 8457    9
 1.000000+0 0.000000+0 1.516400+6 1.900000+3 1.750000-4 1.800000-52871 8457   10
 3.000000+0 0.000000+0 5.672000+4 5.000000+0 9.998250-1 1.800000-52871 8457   11
 0.000000+0 0.000000+0          0          0          6          42871 8457   12
 3.420000-4 0.000000+0 5.690630+1 3.912610+0 0.000000+0 0.000000+02871 8457   13
 5.672000+4 5.000000+0          0          0         12          02871 8457   14
 3.000000+0 0.000000+0 1.000000+0 2.046780-2 0.000000+0 0.000000+02871 8457   15
 2.923000+3 6.138300+1 0.000000+0 0.000000+0 2.117000+3 4.445700+12871 8457   16
 2.959560+5 1.500000-1          0          0         12          02871 8457   17
 1.000000+0 0.000000+0 5.555560-2 5.847950-3 0.000000+0 0.000000+02871 8457   18
 1.060000-1 2.968000-3 6.540000-2 1.831200-3 3.050000-2 8.540000-42871 8457   19
 3.165060+5 1.700000-1          0          0         12          02871 8457   20
 1.000000+0 0.000000+0 2.719300-1 3.508770-2 0.000000+0 0.000000+02871 8457   21
 8.490000-2 2.462100-3 5.370000-2 1.557300-3 2.360000-2 6.844000-42871 8457   22
 6.124620+5 2.600000-1          0          0         12          02871 8457   23
 1.000000+0 0.000000+0 1.169590-2 2.923980-3 0.000000+0 0.000000+02871 8457   24
 1.550000-2 4.960000-4 1.190000-2 3.808000-4 2.780000-3 8.896000-52871 8457   25
 0.000000+0 1.000000+0          0          0          6          32871 8457   26
 1.000000+0 0.000000+0 7.742600+1 6.740740+0 0.000000+0 0.000000+02871 8457   27
 9.039000+5 1.900000+3          0          0          6          02871 8457   28
 1.000000+0 1.000000+0 2.500000-5 3.000000-6 0.000000+0 0.000000+02871 8457   29
 1.200300+6 1.900000+3          0          0          6          02871 8457   30
 1.000000+0 1.000000+0 8.000000-5 1.000000-5 0.000000+0 0.000000+02871 8457   31
 1.516400+6 1.900000+3          0          0          6          02871 8457   32
 1.000000+0 1.000000+0 7.000000-5 1.000000-5 0.000000+0 0.000000+02871 8457   33
 0.000000+0 8.000000+0          0          0          6         162871 8457   34
 1.000000+0 0.000000+0 5.435680+4 5.435680+3 0.000000+0 0.000000+02871 8457   35
 2.558000+3 1.279000+2          0          0          6          02871 8457   36
 3.000000+0 0.000000+0 1.213820+0 1.213820-1 0.000000+0 0.000000+02871 8457   37
 2.658000+3 1.329000+2          0          0          6          02871 8457   38
 1.000000+0 0.000000+0 1.209390-5 1.209390-6 0.000000+0 0.000000+02871 8457   39
 7.059000+3 3.529500+2          0          0          6          02871 8457   40
 3.000000+0 0.000000+0 4.778490-1 4.778490-2 0.000000+0 0.000000+02871 8457   41
 7.240000+3 3.620000+2          0          0          6          02871 8457   42
 1.000000+0 0.000000+0 5.107780-6 5.107780-7 0.000000+0 0.000000+02871 8457   43
 4.550480+4 2.275240+3          0          0          6          02871 8457   44
 3.000000+0 0.000000+0 7.240140-1 7.240140-2 0.000000+0 0.000000+02871 8457   45
 5.416200+4 2.708100+3          0          0          6          02871 8457   46
 3.000000+0 0.000000+0 2.756520-1 2.756520-2 0.000000+0 0.000000+02871 8457   47
 5.741700+4 2.870850+3          0          0          6          02871 8457   48
 1.000000+0 0.000000+0 2.325190-7 2.325190-8 0.000000+0 0.000000+02871 8457   49
 2.175620+5 1.087810+4          0          0          6          02871 8457   50
 1.000000+0 0.000000+0 1.242600-6 1.242600-7 0.000000+0 0.000000+02871 8457   51
 2.381110+5 1.190560+4          0          0          6          02871 8457   52
 1.000000+0 0.000000+0 4.994100-6 4.994100-7 0.000000+0 0.000000+02871 8457   53
 2.843930+5 1.421960+4          0          0          6          02871 8457   54
 1.000000+0 0.000000+0 5.795000-7 5.795000-8 0.000000+0 0.000000+02871 8457   55
 2.932980+5 1.466490+4          0          0          6          02871 8457   56
 1.000000+0 0.000000+0 1.919000-7 1.919000-8 0.000000+0 0.000000+02871 8457   57
 3.049420+5 1.524710+4          0          0          6          02871 8457   58
 1.000000+0 0.000000+0 2.194800-6 2.194800-7 0.000000+0 0.000000+02871 8457   59
 3.138480+5 1.569240+4          0          0          6          02871 8457   60
 1.000000+0 0.000000+0 7.068000-7 7.068000-8 0.000000+0 0.000000+02871 8457   61
 5.340670+5 2.670340+4          0          0          6          02871 8457   62
 1.000000+0 0.000000+0 4.760000-8 4.760000-9 0.000000+0 0.000000+02871 8457   63
 6.008980+5 3.004490+4          0          0          6          02871 8457   64
 1.000000+0 0.000000+0 1.112000-8 1.112000-9 0.000000+0 0.000000+02871 8457   65
 6.098040+5 3.049020+4          0          0          6          02871 8457   66
 1.000000+0 0.000000+0 3.280000-9 3.28000-10 0.000000+0 0.000000+02871 8457   67
 0.000000+0 9.000000+0          0          0          6          82871 8457   68
 1.000000+0 0.000000+0 2.381450+3 2.381450+2 0.000000+0 0.000000+02871 8457   69
 2.558000+3 5.116000+1          0          0          6          02871 8457   70
 3.000000+0 0.000000+0 2.477180-2 2.477180-3 0.000000+0 0.000000+02871 8457   71
 2.658000+3 5.316000+1          0          0          6          02871 8457   72
 1.000000+0 0.000000+0 2.783760-7 2.783760-8 0.000000+0 0.000000+02871 8457   73
 9.415000+3 1.883000+2          0          0          6          02871 8457   74
 3.000000+0 0.000000+0 2.461650-1 2.461650-2 0.000000+0 0.000000+02871 8457   75
 9.695000+3 1.939000+2          0          0          6          02871 8457   76
 1.000000+0 0.000000+0 2.786780-6 2.786780-7 0.000000+0 0.000000+02871 8457   77
 6.512200+4 1.302440+3          0          0          6          02871 8457   78
 1.000000+0 0.000000+0 1.748360-6 1.748360-7 0.000000+0 0.000000+02871 8457   79
 6.683200+4 1.336640+3          0          0          6          02871 8457   80
 1.000000+0 0.000000+0 2.998900-6 2.998900-7 0.000000+0 0.000000+02871 8457   81
 7.570000+4 1.514000+3          0          0          6          02871 8457   82
 1.000000+0 0.000000+0 1.031620-6 1.031620-7 0.000000+0 0.000000+02871 8457   83
 7.790000+4 1.558000+3          0          0          6          02871 8457   84
 1.000000+0 0.000000+0 2.729000-7 2.729000-8 0.000000+0 0.000000+02871 8457   85
 0.000000+0 0.000000+0          0          0          0          02871 8  099999
 0.000000+0 0.000000+0          0          0          0          02871 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
 7.719200+4 1.903140+2         -1          0          2          12872 1451    1
 1.681400+5 1.000000+0         16          2          0          62872 1451    2
 0.000000+0 0.000000+0          0          0          4        3112872 1451    3
 0.000000+0 0.000000+0          0          0         52          22872 1451    4
 77-Ir-192NHAR+WIN    EVAL-SEP03 A.L. NICHOLS                     2872 1451    5
                      DIST-NOV07                       261107     2872 1451    6
----JEFF-311          MATERIAL 2872                               2872 1451    7
-----RADIOACTIVE DECAY DATA                                       2872 1451    8
------ENDF-6 FORMAT                                               2872 1451    9
******************************************************************2872 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2872 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2872 1451   12
**             Original data taken from:  UKPADD67              **2872 1451   13
******************************************************************2872 1451   14
                                                                  2872 1451   15
     C M Baglin           Nucl Data Sheets 84(1998)717            2872 1451   16
     G Scharff-Goldhaber, M McKeown  Phys Rev Letts 3(1959)47     2872 1451   17
                                     (Egamma, transition type)    2872 1451   18
     G Harbottle          Nucl Phys 41(1963)604 (T1/2)            2872 1451   19
     G Harbottle          Radiochim Acta 13(1970)132 (T1/2)       2872 1451   20
     G Scharff-Goldhaber  Bull Am Phys Soc 22(1977)545, BG1       2872 1451   21
                             (Egamma, ICC, transition type)       2872 1451   22
     F Rosel et al        At Data Nucl Data Tables 21(1978)92     2872 1451   23
                                                        (ICC)     2872 1451   24
                                                                  2872 1451   25
The recommended half-life of 241(9) years represents the          2872 1451   26
measurement of Harbottle (1970), after a value of 650(430)        2872 1451   27
years had been previously proposed (Harbottle (1963)).  Further   2872 1451   28
measurements are required to confirm the validity of this decay   2872 1451   29
parameter.                                                        2872 1451   30
                                                                  2872 1451   31
Scharff-Goldhaber and McKeown (1959) concluded that Ir-192n       2872 1451   32
decays only to the ground state of Ir-192; thus, 12.98-keV        2872 1451   33
nuclear level (6+) has been proposed as an intermediate level     2872 1451   34
in this decay process to give 155.16- and 12.98-keV gamma         2872 1451   35
transitions to the ground state.  A spin and parity of 11- were   2872 1451   36
assigned to the Ir-192n nuclear level at 168.14 keV.  These       2872 1451   37
data and the internal conversion coefficients of Rosel et al      2872 1451   38
were used to determine the two gamma-ray emission                 2872 1451   39
probabilities, with their transition types defined as E5          2872 1451   40
(155.16 keV gamma ray) and E2 (12.98 keV gamma ray).              2872 1451   41
                                                                  2872 1451   42
Further studies are required to confirm the validity of the       2872 1451   43
proposed decay scheme.                                            2872 1451   44
                                                                  2872 1451   45
                                                                  2872 1451   46
      MEAN GAMMA ENERGY              =      0.1504  KEV           2872 1451   47
      MEAN X-RAY ENERGY              =      2.9355  KEV           2872 1451   48
      MEAN AUGER ELECTRON ENERGY     =      9.1115  KEV           2872 1451   49
      MEAN CONVERSION ELECTRON ENERGY=    155.9311  KEV           2872 1451   50
      EFFECTIVE Q VALUE              =    168.1400  KEV           2872 1451   51
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0714                2872 1451   52
      CALCULATED Q VALUE             =    168.1285  KEV           2872 1451   53
      % DEVIATION                    =      0.0069                2872 1451   54
                                                                  2872 1451   55
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2872 1451   56
                                1        451         58          12872 1451   57
                                8        457         48          12872 1451   58
 0.000000+0 0.000000+0          0          0          0          02872 1  099999
 0.000000+0 0.000000+0          0          0          0          02872 0  0    0
 7.719200+4 1.903140+2         16          2          0          32872 8457    1
 7.605220+9 2.840120+8          0          0         34          02872 8457    2
 1.650430+5 1.561970+4 3.085940+3 2.935650+2 0.000000+0 0.000000+02872 8457    3
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 9.111460+3 9.111460+22872 8457    4
 1.559310+5 1.559310+4 1.504210+2 2.796170+0 2.935520+3 2.935520+22872 8457    5
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02872 8457    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02872 8457    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0                      2872 8457    8
 1.100000+1-1.000000+0          0          0          6          12872 8457    9
 3.000000+0 0.000000+0 1.681400+5 1.200000+2 1.000000+0 0.000000+02872 8457   10
 0.000000+0 0.000000+0          0          0          6          22872 8457   11
 9.680000-4 0.000000+0 1.504210+2 2.796170+0 0.000000+0 0.000000+02872 8457   12
 1.298000+4 2.000000+1          0          0         12          02872 8457   13
 3.000000+0 0.000000+0 1.797520-2 3.099170-4 0.000000+0 0.000000+02872 8457   14
 5.732000+4 1.146400+3 0.000000+0 0.000000+0 0.000000+0 0.000000+02872 8457   15
 1.551600+5 1.400000+2          0          0         12          02872 8457   16
 3.000000+0 0.000000+0 1.000000+0 1.859500-2 0.000000+0 0.000000+02872 8457   17
 1.032000+3 1.960800+1 7.000000+0 1.330000-1 7.650000+2 1.453500+12872 8457   18
 0.000000+0 8.000000+0          0          0          6          72872 8457   19
 1.000000+0 0.000000+0 1.650430+5 1.650430+4 0.000000+0 0.000000+02872 8457   20
 2.558000+3 1.279000+2          0          0          6          02872 8457   21
 3.000000+0 0.000000+0 2.197560+0 2.197560-1 0.000000+0 0.000000+02872 8457   22
 7.059000+3 3.529500+2          0          0          6          02872 8457   23
 3.000000+0 0.000000+0 4.923840-1 4.923840-2 0.000000+0 0.000000+02872 8457   24
 1.042200+4 5.211000+2          0          0          6          02872 8457   25
 3.000000+0 0.000000+0 9.973680-1 9.973680-2 0.000000+0 0.000000+02872 8457   26
 5.580500+4 2.790250+3          0          0          6          02872 8457   27
 3.000000+0 0.000000+0 2.574880-4 2.574880-5 0.000000+0 0.000000+02872 8457   28
 7.904900+4 3.952450+3          0          0          6          02872 8457   29
 3.000000+0 0.000000+0 6.776000-3 6.776000-4 0.000000+0 0.000000+02872 8457   30
 1.439450+5 7.197240+3          0          0          6          02872 8457   31
 3.000000+0 0.000000+0 7.405200-1 7.405200-2 0.000000+0 0.000000+02872 8457   32
 1.526020+5 7.630100+3          0          0          6          02872 8457   33
 3.000000+0 0.000000+0 2.516800-1 2.516800-2 0.000000+0 0.000000+02872 8457   34
 0.000000+0 9.000000+0          0          0          6          62872 8457   35
 1.000000+0 0.000000+0 2.935520+3 2.935520+2 0.000000+0 0.000000+02872 8457   36
 2.558000+3 5.116000+1          0          0          6          02872 8457   37
 3.000000+0 0.000000+0 4.484810-2 4.484810-3 0.000000+0 0.000000+02872 8457   38
 9.415000+3 1.883000+2          0          0          6          02872 8457   39
 3.000000+0 0.000000+0 2.536520-1 2.536520-2 0.000000+0 0.000000+02872 8457   40
 6.328700+4 1.265740+3          0          0          6          02872 8457   41
 3.000000+0 0.000000+0 1.880460-3 1.880460-4 0.000000+0 0.000000+02872 8457   42
 6.489600+4 1.297920+3          0          0          6          02872 8457   43
 3.000000+0 0.000000+0 3.236600-3 3.236600-4 0.000000+0 0.000000+02872 8457   44
 7.350000+4 1.470000+3          0          0          6          02872 8457   45
 3.000000+0 0.000000+0 1.113390-3 1.113390-4 0.000000+0 0.000000+02872 8457   46
 7.560000+4 1.512000+3          0          0          6          02872 8457   47
 3.000000+0 0.000000+0 2.880570-4 2.880570-5 0.000000+0 0.000000+02872 8457   48
 0.000000+0 0.000000+0          0          0          0          02872 8  099999
 0.000000+0 0.000000+0          0          0          0          02872 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
 7.719300+4 1.913050+2         -1          0          2          12873 1451    1
 0.000000+0 0.000000+0          0          0          0          62873 1451    2
 0.000000+0 0.000000+0          0          0          4        3112873 1451    3
 0.000000+0 0.000000+0          0          0         22          22873 1451    4
 77-Ir-193 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2873 1451    5
                      DIST-NOV07                       261107     2873 1451    6
----JEFF-311          MATERIAL 2873                               2873 1451    7
-----RADIOACTIVE DECAY DATA                                       2873 1451    8
------ENDF-6 FORMAT                                               2873 1451    9
******************************************************************2873 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2873 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2873 1451   12
**             Original data taken from:  NUBASE                **2873 1451   13
******************************************************************2873 1451   14
******************************************************************2873 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2873 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2873 1451   17
                                                                  2873 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2873 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2873 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2873 1451   21
******************************************************************2873 1451   22
STABLE NUCLEUS                                                    2873 1451   23
       SPIN          1.5                                          2873 1451   24
       PARITY        1.0                                          2873 1451   25
NATURAL ABUNDANCE   62.7 2       %                                2873 1451   26
                                1        451         28          02873 1451   27
                                8        457          5          02873 1451   28
 0.000000+0 0.000000+0          0          0          0          02873 1  099999
                                                                  2873 0  0    0
 7.71930+04 1.91305+02          0          0          1          02873 8457    1
 0.00000+00 0.00000+00          0          0          6          02873 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002873 8457    3
 1.50000+00 1.00000+00          0          0          6          02873 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002873 8457    5
                                                                  2873 8  099999
                                                                  2873 0  0    0
                                                                     0 0  0    0
 7.719300+4 1.913050+2         -1          0          2          12874 1451    1
 8.023600+4 1.000000+0          2          1          0          62874 1451    2
 0.000000+0 0.000000+0          0          0          4        3112874 1451    3
 0.000000+0 0.000000+0          0          0         52          22874 1451    4
 77-Ir-193MHAR+WIN    EVAL-OCT06 A.L. NICHOLS                     2874 1451    5
                      DIST-NOV07                       261107     2874 1451    6
----JEFF-311          MATERIAL 2874                               2874 1451    7
-----RADIOACTIVE DECAY DATA                                       2874 1451    8
------ENDF-6 FORMAT                                               2874 1451    9
******************************************************************2874 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2874 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2874 1451   12
**             Original data taken from:  UKPADD67              **2874 1451   13
******************************************************************2874 1451   14
                                                                  2874 1451   15
     E Achterberg et al       Nucl Data Sheets 107(2006)1         2874 1451   16
     K M Bisgard, R J Hanson  Nucl Phys A125(1969)305 (T1/2)      2874 1451   17
     B P Bayhurst et al       Phys Rev C12(1975)451 (T1/2)        2874 1451   18
     M Lindner et al          Phys Rev C36(1987)1132              2874 1451   19
                              (T1/2, Egamma, ICC)                 2874 1451   20
     N Nica et al             Phys Rev C70(2004)054305            2874 1451   21
                              (T1/2, Egamma, ICC)                 2874 1451   22
     J C Hardy et al          Appl Radiat Isot 64(2006)1392 (ICC) 2874 1451   23
     T Kibedi et al           Proc Int Conf Nucl Data for Sci and 2874 1451   24
                              Technol, 26 Sept - 1 Oct 2004,      2874 1451   25
                              Santa Fe, New Mexico, USA,          2874 1451   26
                              Editors: R C Haight et al,          2874 1451   27
                              AIP Conf Proc 769 (2005)Part 1, 26  2874 1451   28
                              (ICC)                               2874 1451   29
                                                                  2874 1451   30
The recommended half-life of 10.54(4) days is the weighted mean   2874 1451   31
of the measurements of Bisgard and Hanson (1969), Bayhurst et al  2874 1451   32
(1975), and Lindner et al (1987).                                 2874 1451   33
                                                                  2874 1451   34
On the basis of 100% IT decay directly to the Ir-193 ground       2874 1451   35
state, a simple decay scheme has been determined from the         2874 1451   36
theoretical internal conversion coefficients derived from Kibedi  2874 1451   37
et al to calculate the absolute emission probability of the       2874 1451   38
single M4 80.236-keV gamma-ray transition.  The theoretical K-    2874 1451   39
shell internal conversion coefficient of 103.4(15) from Kibedi et 2874 1451   40
al is in excellent agreement with the measured value of 103.0(8)  2874 1451   41
of Nica et al; supportive theoretical calculations by Hardy et al 2874 1451   42
show the most appropriate model to involve the inclusion of the   2874 1451   43
electron hole with frozen atomic orbitals.                        2874 1451   44
                                                                  2874 1451   45
                                                                  2874 1451   46
      MEAN GAMMA ENERGY              =      0.0038  KEV           2874 1451   47
      MEAN X-RAY ENERGY              =      2.5874  KEV           2874 1451   48
      MEAN AUGER ELECTRON ENERGY     =      6.3101  KEV           2874 1451   49
      MEAN CONVERSION ELECTRON ENERGY=     71.3907  KEV           2874 1451   50
      EFFECTIVE Q VALUE              =     80.2360  KEV           2874 1451   51
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0087                2874 1451   52
      CALCULATED Q VALUE             =     80.2921  KEV           2874 1451   53
      % DEVIATION                    =     -0.0699                2874 1451   54
                                                                  2874 1451   55
   ENDF-6  DATA PRODUCED BY COGEND (VERSION DATED - MAR 2004).    2874 1451   56
                                1        451         58          12874 1451   57
                                8        457         43          12874 1451   58
 0.000000+0 0.000000+0          0          0          0          02874 1  099999
 0.000000+0 0.000000+0          0          0          0          02874 0  0    0
 7.719300+4 1.913050+2          2          1          0          32874 8457    1
 9.106560+5 3.456000+3          0          0         34          02874 8457    2
 7.770090+4 7.166900+3 2.591220+3 2.587420+2 0.000000+0 0.000000+02874 8457    3
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 6.310130+3 6.310130+22874 8457    4
 7.139070+4 7.139070+3 3.803190+0 5.616620-2 2.587420+3 2.587420+22874 8457    5
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02874 8457    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02874 8457    7
 0.000000+0 0.000000+0 0.000000+0 0.000000+0                      2874 8457    8
 5.500000+0-1.000000+0          0          0          6          12874 8457    9
 3.000000+0 0.000000+0 8.023600+4 7.000000+0 1.000000+0 0.000000+02874 8457   10
 0.000000+0 0.000000+0          0          0          6          12874 8457   11
 4.740000-5 0.000000+0 3.803190+0 5.616620-2 0.000000+0 0.000000+02874 8457   12
 8.023600+4 7.000000+0          0          0         12          02874 8457   13
 3.000000+0 0.000000+0 1.000000+0 1.476790-2 0.000000+0 0.000000+02874 8457   14
 2.110300+4 2.954420+2 1.030000+2 1.442000+0 1.450000+4 2.030000+22874 8457   15
 0.000000+0 8.000000+0          0          0          6          62874 8457   16
 1.000000+0 0.000000+0 7.770090+4 7.770090+3 0.000000+0 0.000000+02874 8457   17
 2.558000+3 1.279000+2          0          0          6          02874 8457   18
 3.000000+0 0.000000+0 1.203740+0 1.203740-1 0.000000+0 0.000000+02874 8457   19
 4.125000+3 2.062500+2          0          0          6          02874 8457   20
 3.000000+0 0.000000+0 4.882200-3 4.882200-4 0.000000+0 0.000000+02874 8457   21
 7.059000+3 3.529500+2          0          0          6          02874 8457   22
 3.000000+0 0.000000+0 4.562410-1 4.562410-2 0.000000+0 0.000000+02874 8457   23
 5.580500+4 2.790250+3          0          0          6          02874 8457   24
 3.000000+0 0.000000+0 1.855240-4 1.855240-5 0.000000+0 0.000000+02874 8457   25
 6.902080+4 3.451040+3          0          0          6          02874 8457   26
 3.000000+0 0.000000+0 6.873000-1 6.873000-2 0.000000+0 0.000000+02874 8457   27
 7.767800+4 3.883900+3          0          0          6          02874 8457   28
 3.000000+0 0.000000+0 3.081000-1 3.081000-2 0.000000+0 0.000000+02874 8457   29
 0.000000+0 9.000000+0          0          0          6          62874 8457   30
 1.000000+0 0.000000+0 2.587420+3 2.587420+2 0.000000+0 0.000000+02874 8457   31
 2.558000+3 5.116000+1          0          0          6          02874 8457   32
 3.000000+0 0.000000+0 2.456620-2 2.456620-3 0.000000+0 0.000000+02874 8457   33
 9.415000+3 1.883000+2          0          0          6          02874 8457   34
 3.000000+0 0.000000+0 2.350330-1 2.350330-2 0.000000+0 0.000000+02874 8457   35
 6.328700+4 1.265740+3          0          0          6          02874 8457   36
 3.000000+0 0.000000+0 1.354900-3 1.354900-4 0.000000+0 0.000000+02874 8457   37
 6.489600+4 1.297920+3          0          0          6          02874 8457   38
 3.000000+0 0.000000+0 2.332010-3 2.332010-4 0.000000+0 0.000000+02874 8457   39
 7.350000+4 1.470000+3          0          0          6          02874 8457   40
 3.000000+0 0.000000+0 8.022130-4 8.022130-5 0.000000+0 0.000000+02874 8457   41
 7.560000+4 1.512000+3          0          0          6          02874 8457   42
 3.000000+0 0.000000+0 2.075490-4 2.075490-5 0.000000+0 0.000000+02874 8457   43
 0.000000+0 0.000000+0          0          0          0          02874 8  099999
 0.000000+0 0.000000+0          0          0          0          02874 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
 7.719400+4 1.922990+2         -1          0          2          12875 1451    1
 0.000000+0 1.000000+0          0          0          0          62875 1451    2
 0.000000+0 0.000000+0          0          0          4        3112875 1451    3
 0.000000+0 0.000000+0          0          0         70          22875 1451    4
 77-Ir-194 BRK        EVAL-DEC98 E.BROWNE                         2875 1451    5
 /DDEP/               DIST-NOV07                       261107     2875 1451    6
----JEFF-311          MATERIAL 2875                               2875 1451    7
-----RADIOACTIVE DECAY DATA                                       2875 1451    8
------ENDF-6 FORMAT                                               2875 1451    9
******************************************************************2875 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2875 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2875 1451   12
**             Original data taken from:  LNHB                  **2875 1451   13
******************************************************************2875 1451   14
******************************************************************2875 1451   15
*Data from the Laboratoire National Henri Becquerel, BNM-CEA/LNHB*2875 1451   16
*              http://www.nucleide.org/NucData.htm               *2875 1451   17
******************************************************************2875 1451   18
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2875 1451   19
*     (the CEA-Bruyeres version of the RADLST program).          *2875 1451   20
* (1) 0. Bersillon and J. Blachot, to be published.              *2875 1451   21
******************************************************************2875 1451   22
194IR DECAY 19.3 H    1                     I(min) = 0.0E+00 %    2875 1451   23
         Ex = 0.0         keV                     1 decay mode(s) 2875 1451   24
                                                                  2875 1451   25
194IR B- DECAY              Q =  2246.8000 keV       1.6000       2875 1451   26
         Branching                100.0000 %         0.0000       2875 1451   27
                         Br*Q =  2246.8000 keV       1.6000       2875 1451   28
                                              0 isomeric state(s) 2875 1451   29
                                                                  2875 1451   30
Individual beta- transitions                                      2875 1451   31
Final level    end point    shape    av.energy        intensity   2875 1451   32
 2158.050     88.749   1.600  0     23.000   0.400    0.002 0.000 2875 1451   33
 2140.830    105.969   1.600  0     27.700   0.400    0.002 0.000 2875 1451   34
 2134.200    112.599   1.600  0     29.500   0.400    0.046 0.006 2875 1451   35
 2114.170    132.628   1.600  0     35.000   0.500    0.008 0.001 2875 1451   36
 2109.080    137.718   1.600  0     36.500   0.500    0.031 0.004 2875 1451   37
 2085.600    161.198   1.600  0     43.100   0.400    0.007 0.002 2875 1451   38
 2063.810    182.988   1.600  0     49.300   0.500    0.004 0.001 2875 1451   39
 2053.080    193.718   1.600  0     52.400   0.500    0.003 0.001 2875 1451   40
 2043.720    203.077   1.600  0     55.100   0.500    0.009 0.001 2875 1451   41
 1930.250    316.546   1.600  0     89.300   0.500    0.003 0.001 2875 1451   42
 1924.290    322.506   1.600  0     91.200   0.500    0.004 0.001 2875 1451   43
 1893.590    353.206   1.600  0     10.900   0.500    0.021 0.003 2875 1451   44
 1797.355    449.439   1.600  0    132.000   0.500    0.330 0.040 2875 1451   45
 1778.670    468.124   1.600  0    138.200   0.500    0.004 0.001 2875 1451   46
 1670.640    576.153   1.600  0    175.000   0.600    0.072 0.010 2875 1451   47
 1622.130    624.662   1.600  0    192.000   0.600    0.160 0.021 2875 1451   48
 1547.240    699.551   1.600  0    218.700   0.600    0.070 0.009 2875 1451   49
 1511.927    734.864   1.600  0    231.500   0.600    0.560 0.070 2875 1451   50
 1479.200    767.590   1.600  0    243.400   0.600    0.610 0.080 2875 1451   51
 1267.145    979.643   1.600  0    323.100   0.600    1.770 0.230 2875 1451   52
  922.739   1324.045   1.600  0    452.400   0.600    0.300 0.040 2875 1451   53
  621.990   1624.790   1.600  0    582.200   0.700    1.280 0.200 2875 1451   54
  328.449   1918.327   1.600  0    705.400   0.700    9.300 1.300 2875 1451   55
    0.000   2246.772   1.600  0    845.700   0.700   85.400 1.900 2875 1451   56
                                                                  2875 1451   57
         Mean alpha    energy       0.0000 keV       0.0000       2875 1451   58
         Mean beta     energy     806.2145 keV      18.5649       2875 1451   59
         Mean conv. e- energy       4.0298 keV       0.2653       2875 1451   60
         Mean Auger e- energy       0.0674 keV       0.0080       2875 1451   61
         Mean gamma    energy      90.3715 keV                    2875 1451   62
         Mean X        energy       0.6186 keV       0.0376       2875 1451   63
         Mean recoil   energy       0.0268 keV       0.0006       2875 1451   64
         Mean neutrino energy    1345.4902 keV      31.0599       2875 1451   65
         Mean neutron  energy       0.0000 keV       0.0000       2875 1451   66
         Total         energy    2246.8189 keV      36.6675       2875 1451   67
         Q effective             2246.8000 keV       1.6000       2875 1451   68
         diff. mode                 0.0189 keV       0.0008 %     2875 1451   69
                                                                  2875 1451   70
         Mean e- bind. energy       0.7491 keV                    2875 1451   71
         diff. atomic              -0.0632 keV      -8.4311 %     2875 1451   72
         diff. nuclear              0.0821 keV       0.0037 %     2875 1451   73
                                                                  2875 1451   74
                                1        451         76          02875 1451   75
                                8        457        424          02875 1451   76
 0.000000+0 0.000000+0          0          0          0          02875 1  099999
                                                                  2875 0  0    0
 7.71940+04 1.92299+02          0          0          0          42875 8457    1
 6.94800+04 3.60000+02          0          0          6          02875 8457    2
 8.10312+05 1.85668+04 9.09901+04 5.92173+03 0.00000+00 0.00000+002875 8457    3
 1.00000+00-1.00000+00          0          0          6          12875 8457    4
 1.00000+00 0.00000+00 2.24680+06 1.60000+03 1.00000+00 0.00000+002875 8457    5
 0.00000+00 0.00000+00          0          0          6         652875 8457    6
 1.00000-02 0.00000+00 9.03715+04 5.92161+03 0.00000+00 0.00000+002875 8457    7
 1.11400+05 4.00000+02          0          0         12          02875 8457    8
 1.00000+00 0.00000+00 1.70000-03 6.00000-04 0.00000+00 0.00000+002875 8457    9
 4.10000+00 1.00000+00 2.40000+00 1.80144+00 1.30000+00 7.01086-012875 8457   10
 2.02910+05 1.50000+02          0          0         12          02875 8457   11
 1.00000+00 0.00000+00 3.00000-03 8.00000-04 0.00000+00 0.00000+002875 8457   12
 6.80000-02 2.00000-03 5.60000-02 2.61197-03 9.30000-03 4.09684-042875 8457   13
 2.44830+05 5.00000+01          0          0         12          02875 8457   14
 1.00000+00 0.00000+00 7.70000-03 1.10000-03 0.00000+00 0.00000+002875 8457   15
 1.86000-01 6.00000-03 1.02000-01 4.28528-03 6.30000-02 2.75174-032875 8457   16
 2.93541+05 1.40000+01          0          0         12          02875 8457   17
 1.00000+00 0.00000+00 2.50000+00 3.00000-01 0.00000+00 0.00000+002875 8457   18
 1.07000-01 3.00000-03 6.60000-02 2.81432-03 3.10000-02 1.36561-032875 8457   19
 3.00741+05 1.40000+01          0          0         12          02875 8457   20
 1.00000+00 0.00000+00 3.50000-01 5.00000-02 0.00000+00 0.00000+002875 8457   21
 1.03000-01 4.00000-03 6.10000-02 2.71089-03 2.80000-02 1.30599-032875 8457   22
 3.28448+05 1.40000+01          0          0         12          02875 8457   23
 1.00000+00 0.00000+00 1.31000+01 1.70000+00 0.00000+00 0.00000+002875 8457   24
 7.60000-02 2.00000-03 4.90000-02 2.48212-03 2.00000-02 1.16619-032875 8457   25
 3.64867+05 1.50000+01          0          0         12          02875 8457   26
 1.00000+00 0.00000+00 4.10000-02 6.00000-03 0.00000+00 0.00000+002875 8457   27
 5.68000-02 1.70000-03 3.80000-02 1.10589-02 1.40000-02 1.08462-032875 8457   28
 4.82857+05 2.60000+01          0          0         12          02875 8457   29
 1.00000+00 0.00000+00 4.60000-02 6.00000-03 0.00000+00 0.00000+002875 8457   30
 2.72000-02 8.00000-04 2.00000-02 8.48528-04 5.60000-03 2.61197-042875 8457   31
 5.30173+05 3.00000+01          0          0         12          02875 8457   32
 1.00000+00 0.00000+00 1.60000-02 2.00000-03 0.00000+00 0.00000+002875 8457   33
 7.35000-03 2.20000-04 6.10000-03 2.71089-04 9.40000-04 4.11733-052875 8457   34
 5.89179+05 1.70000+01          0          0         12          02875 8457   35
 1.00000+00 0.00000+00 1.40000-01 1.80000-02 0.00000+00 0.00000+002875 8457   36
 2.31000-02 2.40000-03 1.81000-02 7.38139-04 3.70000-03 3.19877-042875 8457   37
 5.94291+05 1.90000+01          0          0         12          02875 8457   38
 1.00000+00 0.00000+00 6.20000-02 8.00000-03 0.00000+00 0.00000+002875 8457   39
 1.66000-02 5.00000-04 1.26000-02 5.50349-04 3.00000-03 1.34536-042875 8457   40
 6.07610+05 8.00000+01          0          0         12          02875 8457   41
 1.00000+00 0.00000+00 3.90000-03 6.00000-04 0.00000+00 0.00000+002875 8457   42
 1.58000-02 5.00000-04 1.21000-02 5.40156-04 2.80000-03 1.30599-042875 8457   43
 6.21290+05 1.50000+02          0          0         12          02875 8457   44
 1.00000+00 0.00000+00 9.60000-03 1.80000-03 0.00000+00 0.00000+002875 8457   45
 9.10000-03 1.80000-03 7.40000-03 1.51634-03 1.30000-03 3.02524-042875 8457   46
 6.21971+05 1.90000+01          0          0         12          02875 8457   47
 1.00000+00 0.00000+00 3.30000-01 5.00000-02 0.00000+00 0.00000+002875 8457   48
 1.50000-02 5.00000-04 1.15000-02 5.28228-04 2.50000-03 1.25000-042875 8457   49
 6.45146+05 2.00000+01          0          0         12          02875 8457   50
 1.00000+00 0.00000+00 1.18000+00 1.60000-01 0.00000+00 0.00000+002875 8457   51
 1.38000-02 4.00000-04 1.06000-02 4.37177-04 2.40000-03 1.23223-042875 8457   52
 6.99500+05 4.00000+02          0          0         12          02875 8457   53
 1.00000+00 0.00000+00 2.50000-03 1.30000-03 0.00000+00 0.00000+002875 8457   54
 2.30000-02 1.10000-02 1.90000-02 1.00162-02 3.20000-03 1.40329-032875 8457   55
 7.00550+05 4.00000+01          0          0         12          02875 8457   56
 1.00000+00 0.00000+00 2.60000-02 5.00000-03 0.00000+00 0.00000+002875 8457   57
 1.15000-02 4.00000-04 8.90000-03 4.01608-04 1.90000-03 1.15104-042875 8457   58
 8.10660+05 1.90000+02          0          0         12          02875 8457   59
 1.00000+00 0.00000+00 2.50000-03 6.00000-04 0.00000+00 0.00000+002875 8457   60
 3.20000-03 1.00000-04 2.70000-03 1.28690-04 0.00000+00 0.00000+002875 8457   61
 8.57120+05 1.90000+02          0          0         12          02875 8457   62
 1.00000+00 0.00000+00 7.10000-03 1.20000-03 0.00000+00 0.00000+002875 8457   63
 7.50000-03 2.00000-04 6.00000-03 2.69072-04 0.00000+00 0.00000+002875 8457   64
 8.59450+05 1.80000+02          0          0         12          02875 8457   65
 1.00000+00 0.00000+00 1.70000-03 8.00000-04 0.00000+00 0.00000+002875 8457   66
 7.50000-03 2.00000-04 6.00000-03 2.69072-04 0.00000+00 0.00000+002875 8457   67
 8.89980+05 4.00000+01          0          0         12          02875 8457   68
 1.00000+00 0.00000+00 5.10000-02 7.00000-03 0.00000+00 0.00000+002875 8457   69
 1.05000-02 1.70000-03 8.50000-03 1.42303-03 1.50000-03 2.05000-042875 8457   70
 9.25260+05 6.00000+01          0          0         12          02875 8457   71
 1.00000+00 0.00000+00 1.26000-02 1.80000-03 0.00000+00 0.00000+002875 8457   72
 6.50000-03 2.00000-04 5.20000-03 2.53645-04 0.00000+00 0.00000+002875 8457   73
 9.38690+05 2.50000+01          0          0         12          02875 8457   74
 1.00000+00 0.00000+00 6.00000-01 8.00000-02 0.00000+00 0.00000+002875 8457   75
 6.27000-03 1.90000-04 5.00000-03 2.50000-04 9.00000-04 4.03609-052875 8457   76
 1.00012+06 4.00000+01          0          0         12          02875 8457   77
 1.00000+00 0.00000+00 4.70000-02 6.00000-03 0.00000+00 0.00000+002875 8457   78
 8.30000-03 1.80000-03 6.80000-03 1.51381-03 1.13000-03 2.12719-042875 8457   79
 1.04864+06 5.00000+01          0          0         12          02875 8457   80
 1.00000+00 0.00000+00 2.60000-02 4.00000-03 0.00000+00 0.00000+002875 8457   81
 1.10000-02 1.00000-03 7.70000-03 2.41109-03 1.20000-03 4.00016-032875 8457   82
 1.10405+06 5.00000+01          0          0         12          02875 8457   83
 1.00000+00 0.00000+00 2.60000-02 4.00000-03 0.00000+00 0.00000+002875 8457   84
 1.78000-03 5.00000-05 1.49000-03 6.70678-05 0.00000+00 0.00000+002875 8457   85
 1.15075+06 5.00000+01          0          0         12          02875 8457   86
 1.00000+00 0.00000+00 6.00000-01 8.00000-02 0.00000+00 0.00000+002875 8457   87
 4.20000-03 1.30000-04 3.42000-03 1.43272-04 0.00000+00 0.00000+002875 8457   88
 1.15660+06 3.00000+02          0          0         12          02875 8457   89
 1.00000+00 0.00000+00 1.80000-03 5.00000-04 0.00000+00 0.00000+002875 8457   90
 8.80000-03 1.90000-03 7.30000-03 1.61492-03 0.00000+00 0.00000+002875 8457   91
 1.17538+06 5.00000+01          0          0         12          02875 8457   92
 1.00000+00 0.00000+00 6.10000-02 8.00000-03 0.00000+00 0.00000+002875 8457   93
 1.59000-03 5.00000-05 1.33000-03 5.64979-05 0.00000+00 0.00000+002875 8457   94
 1.18349+06 5.00000+01          0          0         12          02875 8457   95
 1.00000+00 0.00000+00 3.10000-01 4.00000-02 0.00000+00 0.00000+002875 8457   96
 5.79000-03 1.70000-04 4.76000-03 1.99980-04 0.00000+00 0.00000+002875 8457   97
 1.18640+06 4.00000+02          0          0         12          02875 8457   98
 1.00000+00 0.00000+00 8.40000-03 1.90000-03 0.00000+00 0.00000+002875 8457   99
 5.60000-03 1.70000-03 4.60000-03 1.40678-03 0.00000+00 0.00000+002875 8457  100
 1.21878+06 5.00000+01          0          0         12          02875 8457  101
 1.00000+00 0.00000+00 5.60000-02 8.00000-03 0.00000+00 0.00000+002875 8457  102
 3.76000-03 1.10000-04 3.07000-03 1.28773-04 0.00000+00 0.00000+002875 8457  103
 1.29367+06 6.00000+01          0          0         12          02875 8457  104
 1.00000+00 0.00000+00 4.60000-02 7.00000-03 0.00000+00 0.00000+002875 8457  105
 2.00000-02 1.00000-02 1.60000-02 8.01439-03 0.00000+00 0.00000+002875 8457  106
 1.30815+06 1.20000+02          0          0         12          02875 8457  107
 1.00000+00 0.00000+00 1.30000-03 2.20000-04 0.00000+00 0.00000+002875 8457  108
 3.90000-03 6.00000-04 3.20000-03 5.09133-04 0.00000+00 0.00000+002875 8457  109
 1.34216+06 6.00000+01          0          0         12          02875 8457  110
 1.00000+00 0.00000+00 3.80000-02 5.00000-03 0.00000+00 0.00000+002875 8457  111
 5.00000-03 2.00000-03 4.00000-03 1.50479-03 0.00000+00 0.00000+002875 8457  112
 1.42148+06 2.80000+02          0          0         12          02875 8457  113
 1.00000+00 0.00000+00 6.30000-04 2.10000-04 0.00000+00 0.00000+002875 8457  114
 5.20000-03 1.30000-03 4.30000-03 1.00829-03 0.00000+00 0.00000+002875 8457  115
 1.43135+06 3.40000+02          0          0         12          02875 8457  116
 1.00000+00 0.00000+00 2.20000-03 7.00000-04 0.00000+00 0.00000+002875 8457  117
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002875 8457  118
 1.43252+06 1.20000+02          0          0         12          02875 8457  119
 1.00000+00 0.00000+00 1.10000-03 3.00000-04 0.00000+00 0.00000+002875 8457  120
 5.71000-03 1.70000-04 4.55000-03 1.95531-04 0.00000+00 0.00000+002875 8457  121
 1.44178+06 1.40000+02          0          0         12          02875 8457  122
 1.00000+00 0.00000+00 1.50000-03 3.00000-04 0.00000+00 0.00000+002875 8457  123
 4.10000-03 5.00000-04 3.40000-03 4.12800-04 0.00000+00 0.00000+002875 8457  124
 1.45023+06 1.10000+02          0          0         12          02875 8457  125
 1.00000+00 0.00000+00 1.60000-03 3.00000-04 0.00000+00 0.00000+002875 8457  126
 4.00000-03 3.00000-04 3.30000-03 3.15913-04 0.00000+00 0.00000+002875 8457  127
 1.46350+06 1.50000+02          0          0         12          02875 8457  128
 1.00000+00 0.00000+00 5.90000-03 1.40000-03 0.00000+00 0.00000+002875 8457  129
 2.67000-03 8.00000-05 2.20000-03 9.62081-05 0.00000+00 0.00000+002875 8457  130
 1.46891+06 7.00000+01          0          0         12          02875 8457  131
 1.00000+00 0.00000+00 1.90000-01 3.00000-02 0.00000+00 0.00000+002875 8457  132
 1.09000-03 3.00000-05 9.20000-04 4.07647-05 0.00000+00 0.00000+002875 8457  133
 1.48705+06 8.00000+01          0          0         12          02875 8457  134
 1.00000+00 0.00000+00 1.70000-02 2.30000-03 0.00000+00 0.00000+002875 8457  135
 4.50000-03 1.20000-03 3.70000-03 1.00614-03 0.00000+00 0.00000+002875 8457  136
 1.49218+06 1.30000+02          0          0         12          02875 8457  137
 1.00000+00 0.00000+00 1.50000-03 3.00000-04 0.00000+00 0.00000+002875 8457  138
 4.50000-03 1.20000-03 3.70000-03 1.00614-03 0.00000+00 0.00000+002875 8457  139
 1.51198+06 1.00000+02          0          0         12          02875 8457  140
 1.00000+00 0.00000+00 2.40000-02 4.00000-03 0.00000+00 0.00000+002875 8457  141
 2.49000-03 7.00000-05 2.08000-03 8.65665-05 0.00000+00 0.00000+002875 8457  142
 1.51215+06 2.10000+02          0          0         12          02875 8457  143
 1.00000+00 0.00000+00 1.32000-02 1.80000-03 0.00000+00 0.00000+002875 8457  144
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002875 8457  145
 1.51876+06 1.40000+02          0          0         12          02875 8457  146
 1.00000+00 0.00000+00 1.70000-03 3.00000-04 0.00000+00 0.00000+002875 8457  147
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002875 8457  148
 1.56515+06 8.00000+01          0          0         12          02875 8457  149
 1.00000+00 0.00000+00 2.10000-02 3.00000-03 0.00000+00 0.00000+002875 8457  150
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002875 8457  151
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 1.36339+06 1.40002+02          0          0          6          02875 8457  399
 1.00000+00 0.00000+00 5.10000-06 1.19323-06 0.00000+00 0.00000+002875 8457  400
 1.37184+06 1.10002+02          0          0          6          02875 8457  401
 1.00000+00 0.00000+00 5.28000-06 1.11157-06 0.00000+00 0.00000+002875 8457  402
 1.38511+06 1.50002+02          0          0          6          02875 8457  403
 1.00000+00 0.00000+00 1.29800-05 3.13187-06 0.00000+00 0.00000+002875 8457  404
 1.39052+06 7.00035+01          0          0          6          02875 8457  405
 1.00000+00 0.00000+00 1.74800-04 2.86662-05 0.00000+00 0.00000+002875 8457  406
 1.40081+06 0.00000+00          0          0          6          02875 8457  407
 1.00000+00 0.00000+00 2.20000-02 3.00000-03 0.00000+00 0.00000+002875 8457  408
 1.40866+06 8.00031+01          0          0          6          02875 8457  409
 1.00000+00 0.00000+00 6.29000-05 1.91045-05 0.00000+00 0.00000+002875 8457  410
 1.41379+06 1.30002+02          0          0          6          02875 8457  411
 1.00000+00 0.00000+00 5.55000-06 1.87345-06 0.00000+00 0.00000+002875 8457  412
 1.43359+06 1.00002+02          0          0          6          02875 8457  413
 1.00000+00 0.00000+00 4.99200-05 8.57548-06 0.00000+00 0.00000+002875 8457  414
 0.00000+00 9.00000+00          0          0          6          42875 8457  415
 1.00000-02 0.00000+00 6.18580+02 3.75953+01 0.00000+00 0.00000+002875 8457  416
 9.44000+03 0.00000+00          0          0          6          02875 8457  417
 1.00000+00 0.00000+00 3.76780-01 5.25025-02 0.00000+00 0.00000+002875 8457  418
 6.51220+04 2.00000+00          0          0          6          02875 8457  419
 1.00000+00 0.00000+00 2.46744-01 2.60447-02 0.00000+00 0.00000+002875 8457  420
 6.68320+04 2.00000+00          0          0          6          02875 8457  421
 1.00000+00 0.00000+00 4.23232-01 4.44493-02 0.00000+00 0.00000+002875 8457  422
 7.57000+04 0.00000+00          0          0          6          02875 8457  423
 1.00000+00 0.00000+00 1.84243-01 1.95360-02 0.00000+00 0.00000+002875 8457  424
                                                                  2875 8  099999
                                                                  2875 0  0    0
                                                                     0 0  0    0
 7.719400+4 1.922990+2         -1          0          2          12876 1451    1
 1.470780+5 1.000000+0          1          1          0          62876 1451    2
 0.000000+0 0.000000+0          0          0          4        3112876 1451    3
 0.000000+0 0.000000+0          0          0         40          22876 1451    4
 77-Ir-194MENSDF      EVAL-JUN06 CONVERSION OF ENSDF              2876 1451    5
 /ENSDF/              DIST-NOV07                       261107     2876 1451    6
----JEFF-311          MATERIAL 2876                               2876 1451    7
-----RADIOACTIVE DECAY DATA                                       2876 1451    8
------ENDF-6 FORMAT                                               2876 1451    9
******************************************************************2876 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2876 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2876 1451   12
**             Original data taken from:  ENSDF                 **2876 1451   13
******************************************************************2876 1451   14
******************************************************************2876 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2876 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2876 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2876 1451   18
******************************************************************2876 1451   19
194IR DECAY 31.85 MS 24                     I(min) = 0.0E+00 %    2876 1451   20
         Ex = 147.078   5 keV                     1 decay mode(s) 2876 1451   21
                                                                  2876 1451   22
194IR IT DECAY              Q =   147.0780 keV       0.0050       2876 1451   23
         Branching                100.0000 %         0.0000       2876 1451   24
                         Br*Q =   147.0780 keV       0.0050       2876 1451   25
                                              0 isomeric state(s) 2876 1451   26
                                                                  2876 1451   27
         Mean alpha    energy       0.0000 keV       0.0000       2876 1451   28
         Mean beta     energy       0.0000 keV       0.0000       2876 1451   29
         Mean conv. e- energy      75.1064 keV       3.3993       2876 1451   30
         Mean Auger e- energy       8.1013 keV       0.7014       2876 1451   31
         Mean gamma    energy      13.9365 keV                    2876 1451   32
         Mean X        energy      39.3609 keV       1.9306       2876 1451   33
         Mean recoil   energy       0.0000 keV       0.0000       2876 1451   34
         Mean neutrino energy       0.0000 keV       0.0000       2876 1451   35
         Mean neutron  energy       0.0000 keV       0.0000       2876 1451   36
         Total         energy     136.5052 keV       4.0669       2876 1451   37
         Q effective              147.0780 keV       0.0050       2876 1451   38
         diff. mode               -10.5728 keV      -7.1885 %     2876 1451   39
                                                                  2876 1451   40
         Mean e- bind. energy      56.5830 keV                    2876 1451   41
         diff. atomic              -9.1207 keV     -16.1192 %     2876 1451   42
         diff. nuclear             -1.4521 keV      -0.9873 %     2876 1451   43
                                                                  2876 1451   44
                                1        451         46          02876 1451   45
                                8        457        100          02876 1451   46
 0.000000+0 0.000000+0          0          0          0          02876 1  099999
                                                                  2876 0  0    0
 7.71940+04 1.92299+02          1          1          0          32876 8457    1
 3.18500-02 2.40000-04          0          0          6          02876 8457    2
 8.32078+04 3.47087+03 5.32975+04 2.11955+03 0.00000+00 0.00000+002876 8457    3
 4.00000+00 1.00000+00          0          0          6          12876 8457    4
 3.00000+00 0.00000+00 1.47078+05 5.00000+00 1.00000+00 0.00000+002876 8457    5
 0.00000+00 0.00000+00          0          0          6          92876 8457    6
 1.00000-02 0.00000+00 1.39365+04 8.74862+02 0.00000+00 0.00000+002876 8457    7
 2.79300+04 3.00000+01          0          0         12          02876 8457    8
 3.00000+00 0.00000+00 2.15800-02 4.34885-03 0.00000+00 0.00000+002876 8457    9
 4.75000+01 0.00000+00 0.00000+00 0.00000+00 3.64000+01 1.09200+002876 8457   10
 2.98900+04 6.00000+00          0          0         12          02876 8457   11
 3.00000+00 0.00000+00 1.66000-01 1.29958-02 0.00000+00 0.00000+002876 8457   12
 3.95000+01 0.00000+00 0.00000+00 0.00000+00 3.03000+01 9.09000-012876 8457   13
 3.48400+04 2.00000+01          0          0         12          02876 8457   14
 3.00000+00 0.00000+00 2.40700-02 2.20411-03 0.00000+00 0.00000+002876 8457   15
 1.91500+03 0.00000+00 0.00000+00 0.00000+00 1.41600+03 4.24800+012876 8457   16
 3.92170+04 1.00000+00          0          0         12          02876 8457   17
 3.00000+00 0.00000+00 1.24500-01 1.11866-02 0.00000+00 0.00000+002876 8457   18
 1.75000+01 0.00000+00 0.00000+00 0.00000+00 1.34000+01 4.02000-012876 8457   19
 4.31190+04 1.00000+00          0          0         12          02876 8457   20
 3.00000+00 0.00000+00 1.57700-01 5.06980-02 0.00000+00 0.00000+002876 8457   21
 1.40000+01 5.00000+00 0.00000+00 0.00000+00 1.10000+01 3.01810+002876 8457   22
 6.27930+04 3.00000+00          0          0         12          02876 8457   23
 3.00000+00 0.00000+00 3.98400-01 5.52815-02 0.00000+00 0.00000+002876 8457   24
 1.35000+02 0.00000+00 0.00000+00 0.00000+00 9.99000+01 2.99700+002876 8457   25
 8.23390+04 2.00000+00          0          0         12          02876 8457   26
 3.00000+00 0.00000+00 3.65200-01 3.32266-02 0.00000+00 0.00000+002876 8457   27
 1.11000+01 0.00000+00 9.19000+00 2.75700-01 1.51000+00 4.53000-022876 8457   28
 8.42880+04 2.00000+00          0          0         12          02876 8457   29
 3.00000+00 0.00000+00 4.61480+00 5.70340-01 0.00000+00 0.00000+002876 8457   30
 1.08000+01 0.00000+00 7.60000+00 2.28000-01 2.40000+00 7.20000-022876 8457   31
 1.12230+05 1.00000+00          0          0         12          02876 8457   32
 3.00000+00 0.00000+00 8.30000+00 6.49788-01 0.00000+00 0.00000+002876 8457   33
 3.64000+00 0.00000+00 1.95000+00 5.85000-02 1.27000+00 3.81000-022876 8457   34
 0.00000+00 8.00000+00          0          0          6         272876 8457   35
 1.00000-02 0.00000+00 8.32078+04 3.47087+03 0.00000+00 0.00000+002876 8457   36
 6.22800+03 2.06155+00          0          0          6          02876 8457   37
 3.00000+00 0.00000+00 3.35619+00 3.21524-01 0.00000+00 0.00000+002876 8457   38
 7.06000+03 0.00000+00          0          0          6          02876 8457   39
 3.00000+00 0.00000+00 1.00169+02 7.03215+00 0.00000+00 0.00000+002876 8457   40
 8.17700+03 2.06155+00          0          0          6          02876 8457   41
 3.00000+00 0.00000+00 3.50725+01 4.46046+00 0.00000+00 0.00000+002876 8457   42
 1.45115+04 3.00015+01          0          0          6          02876 8457   43
 3.00000+00 0.00000+00 7.85512-01 1.60043-01 0.00000+00 0.00000+002876 8457   44
 1.64715+04 6.00750+00          0          0          6          02876 8457   45
 3.00000+00 0.00000+00 5.02980+00 4.21693-01 0.00000+00 0.00000+002876 8457   46
 2.14215+04 2.00022+01          0          0          6          02876 8457   47
 3.00000+00 0.00000+00 3.40831+01 3.28424+00 0.00000+00 0.00000+002876 8457   48
 2.47563+04 3.00082+01          0          0          6          02876 8457   49
 3.00000+00 0.00000+00 1.81488-01 3.69769-02 0.00000+00 0.00000+002876 8457   50
 2.57985+04 1.04403+00          0          0          6          02876 8457   51
 3.00000+00 0.00000+00 1.66830+00 1.58035-01 0.00000+00 0.00000+002876 8457   52
 2.67163+04 6.04070+00          0          0          6          02876 8457   53
 3.00000+00 0.00000+00 1.15038+00 9.64467-02 0.00000+00 0.00000+002876 8457   54
 2.97005+04 1.04403+00          0          0          6          02876 8457   55
 3.00000+00 0.00000+00 1.73470+00 7.33169-01 0.00000+00 0.00000+002876 8457   56
 3.16663+04 2.00122+01          0          0          6          02876 8457   57
 3.00000+00 0.00000+00 9.02625+00 8.69768-01 0.00000+00 0.00000+002876 8457   58
 3.60433+04 1.22066+00          0          0          6          02876 8457   59
 3.00000+00 0.00000+00 3.84705-01 3.64424-02 0.00000+00 0.00000+002876 8457   60
 3.61190+04 1.11803+00          0          0          6          02876 8457   61
 3.00000+00 0.00000+00 1.61850+01 1.35693+00 0.00000+00 0.00000+002876 8457   62
 3.99453+04 1.22066+00          0          0          6          02876 8457   63
 3.00000+00 0.00000+00 3.94250-01 1.68494-01 0.00000+00 0.00000+002876 8457   64
 4.93745+04 3.01496+00          0          0          6          02876 8457   65
 3.00000+00 0.00000+00 3.98002+01 5.65022+00 0.00000+00 0.00000+002876 8457   66
 4.96000+04 0.00000+00          0          0          6          02876 8457   67
 3.00000+00 0.00000+00 2.07532+00 9.98958-01 0.00000+00 0.00000+002876 8457   68
 5.96193+04 3.08058+00          0          0          6          02876 8457   69
 3.00000+00 0.00000+00 1.02389+01 1.45356+00 0.00000+00 0.00000+002876 8457   70
 6.21029+04 3.02655+00          0          0          6          02876 8457   71
 3.00000+00 0.00000+00 3.65731+00 5.19209-01 0.00000+00 0.00000+002876 8457   72
 6.89205+04 2.02237+00          0          0          6          02876 8457   73
 3.00000+00 0.00000+00 5.51452-01 5.28294-02 0.00000+00 0.00000+002876 8457   74
 7.08695+04 2.02237+00          0          0          6          02876 8457   75
 3.00000+00 0.00000+00 1.10755+01 1.40857+00 0.00000+00 0.00000+002876 8457   76
 7.91653+04 2.11896+00          0          0          6          02876 8457   77
 3.00000+00 0.00000+00 1.26359-01 1.21053-02 0.00000+00 0.00000+002876 8457   78
 8.11143+04 2.11896+00          0          0          6          02876 8457   79
 3.00000+00 0.00000+00 2.76888+00 3.52142-01 0.00000+00 0.00000+002876 8457   80
 8.16489+04 2.03961+00          0          0          6          02876 8457   81
 3.00000+00 0.00000+00 3.46940-02 3.32370-03 0.00000+00 0.00000+002876 8457   82
 8.35979+04 2.03961+00          0          0          6          02876 8457   83
 3.00000+00 0.00000+00 7.84516-01 9.97735-02 0.00000+00 0.00000+002876 8457   84
 9.88115+04 1.04403+00          0          0          6          02876 8457   85
 3.00000+00 0.00000+00 1.05410+01 8.83747-01 0.00000+00 0.00000+002876 8457   86
 1.09056+05 1.22066+00          0          0          6          02876 8457   87
 3.00000+00 0.00000+00 2.63110+00 2.20589-01 0.00000+00 0.00000+002876 8457   88
 1.11540+05 1.07703+00          0          0          6          02876 8457   89
 3.00000+00 0.00000+00 8.21700-01 6.88905-02 0.00000+00 0.00000+002876 8457   90
 0.00000+00 9.00000+00          0          0          6          42876 8457   91
 1.00000-02 0.00000+00 3.93609+04 1.93057+03 0.00000+00 0.00000+002876 8457   92
 9.18000+03 0.00000+00          0          0          6          02876 8457   93
 3.00000+00 0.00000+00 4.93372+01 5.21855+00 0.00000+00 0.00000+002876 8457   94
 6.32867+04 7.00000-01          0          0          6          02876 8457   95
 3.00000+00 0.00000+00 1.51667+01 1.34510+00 0.00000+00 0.00000+002876 8457   96
 6.48956+04 7.00000-01          0          0          6          02876 8457   97
 3.00000+00 0.00000+00 2.61045+01 2.29844+00 0.00000+00 0.00000+002876 8457   98
 7.36000+04 0.00000+00          0          0          6          02876 8457   99
 3.00000+00 0.00000+00 1.12671+01 1.00591+00 0.00000+00 0.00000+002876 8457  100
                                                                  2876 8  099999
                                                                  2876 0  0    0
                                                                     0 0  0    0
 7.719400+4 1.922990+2         -1          0          2          12877 1451    1
 3.700000+5 1.000000+0          2          2          0          62877 1451    2
 0.000000+0 0.000000+0          0          0          4        3112877 1451    3
 0.000000+0 0.000000+0          0          0         45          22877 1451    4
 77-Ir-194NENSDF      EVAL-NOV96 CONVERSION OF ENSDF              2877 1451    5
 /ENSDF/              DIST-NOV07                       261107     2877 1451    6
----JEFF-311          MATERIAL 2877                               2877 1451    7
-----RADIOACTIVE DECAY DATA                                       2877 1451    8
------ENDF-6 FORMAT                                               2877 1451    9
******************************************************************2877 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2877 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2877 1451   12
**             Original data taken from:  ENSDF                 **2877 1451   13
******************************************************************2877 1451   14
******************************************************************2877 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2877 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2877 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2877 1451   18
******************************************************************2877 1451   19
194IR DECAY 171 D   11                      I(min) = 0.0E+00 %    2877 1451   20
         Ex = 370.        keV                     1 decay mode(s) 2877 1451   21
                                                                  2877 1451   22
194IR B- DECAY              Q =  2616.8000 keV       1.6000       2877 1451   23
         Branching                100.0000 %         0.0000       2877 1451   24
                         Br*Q =  2616.8000 keV       1.6000       2877 1451   25
                                              0 isomeric state(s) 2877 1451   26
                                                                  2877 1451   27
Individual beta- transitions                                      2877 1451   28
Final level    end point    shape    av.energy        intensity   2877 1451   29
 2438.300    178.498   1.887  0      0.000   0.000   97.000 3.000 2877 1451   30
 2423.400    193.398   1.836  0      0.000   0.000    3.000 3.000 2877 1451   31
                                                                  2877 1451   32
         Mean alpha    energy       0.0000 keV       0.0000       2877 1451   33
         Mean beta     energy       0.0000 keV       0.0000       2877 1451   34
         Mean conv. e- energy      81.1084 keV       1.9223       2877 1451   35
         Mean Auger e- energy       1.9510 keV       0.1649       2877 1451   36
         Mean gamma    energy    2321.3851 keV                    2877 1451   37
         Mean X        energy      12.3141 keV       0.3046       2877 1451   38
         Mean recoil   energy       0.0022 keV       0.0001       2877 1451   39
         Mean neutrino energy     178.9448 keV       7.8954       2877 1451   40
         Mean neutron  energy       0.0000 keV       0.0000       2877 1451   41
         Total         energy    2595.7090 keV      62.9397       2877 1451   42
         Q effective             2616.8000 keV       1.6000       2877 1451   43
         diff. mode               -21.0910 keV      -0.8060 %     2877 1451   44
                                                                  2877 1451   45
         Mean e- bind. energy      16.4047 keV                    2877 1451   46
         diff. atomic              -2.1396 keV     -13.0426 %     2877 1451   47
         diff. nuclear            -18.9514 keV      -0.7242 %     2877 1451   48
                                                                  2877 1451   49
                                1        451         51          02877 1451   50
                                8        457        118          02877 1451   51
 0.000000+0 0.000000+0          0          0          0          02877 1  099999
                                                                  2877 0  0    0
 7.71940+04 1.92299+02          2          2          0          42877 8457    1
 1.47744+07 9.50400+05          0          0          6          02877 8457    2
 8.30595+04 1.92931+03 2.33370+06 6.24127+04 0.00000+00 0.00000+002877 8457    3
-7.77770+01 0.00000+00          0          0          6          12877 8457    4
 1.00000+00 0.00000+00 2.61680+06 1.60000+03 1.00000+00 0.00000+002877 8457    5
 0.00000+00 0.00000+00          0          0          6         112877 8457    6
 1.00000-02 0.00000+00 2.32139+06 6.24120+04 0.00000+00 0.00000+002877 8457    7
 1.11700+05 5.00000+02          0          0         12          02877 8457    8
 1.00000+00 0.00000+00 8.90000+00 5.98352-01 0.00000+00 0.00000+002877 8457    9
 3.17000+00 0.00000+00 6.25000-01 1.87500-02 1.90000+00 5.70000-022877 8457   10
 3.24000+05 5.00000+02          0          0         12          02877 8457   11
 1.00000+00 0.00000+00 2.00000+00 1.00000-01 0.00000+00 0.00000+002877 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002877 8457   13
 3.28500+05 5.00000+02          0          0         12          02877 8457   14
 1.00000+00 0.00000+00 9.30000+01 6.82807+00 0.00000+00 0.00000+002877 8457   15
 7.63000-02 0.00000+00 4.92000-02 1.47600-03 2.05000-02 6.15000-042877 8457   16
 3.38800+05 5.00000+02          0          0         12          02877 8457   17
 1.00000+00 0.00000+00 5.50000+01 4.06971+00 0.00000+00 0.00000+002877 8457   18
 6.99000-02 0.00000+00 4.56000-02 1.36800-03 1.83000-02 5.49000-042877 8457   19
 3.90800+05 5.00000+02          0          0         12          02877 8457   20
 1.00000+00 0.00000+00 3.50000+01 2.65754+00 0.00000+00 0.00000+002877 8457   21
 1.42000-02 0.00000+00 1.18000-02 3.54000-04 1.86000-03 5.58000-052877 8457   22
 4.82600+05 5.00000+02          0          0         12          02877 8457   23
 1.00000+00 0.00000+00 9.70000+01 6.96581+00 0.00000+00 0.00000+002877 8457   24
 2.72000-02 0.00000+00 1.99000-02 5.97000-04 5.57000-03 1.67100-042877 8457   25
 5.62400+05 5.00000+02          0          0         12          02877 8457   26
 1.00000+00 0.00000+00 3.50000+01 2.65754+00 0.00000+00 0.00000+002877 8457   27
 1.89000-02 0.00000+00 1.42000-02 4.26000-04 3.51000-03 1.05300-042877 8457   28
 5.62400+05 5.00000+02          0          0         12          02877 8457   29
 1.00000+00 0.00000+00 3.50000+01 2.65754+00 0.00000+00 0.00000+002877 8457   30
 6.50000-03 0.00000+00 5.40000-03 1.62000-04 8.25000-04 2.47500-052877 8457   31
 6.00500+05 5.00000+02          0          0         12          02877 8457   32
 1.00000+00 0.00000+00 6.20000+01 4.31393+00 0.00000+00 0.00000+002877 8457   33
 1.62000-02 0.00000+00 1.24000-02 3.72000-04 2.91000-03 8.73000-052877 8457   34
 6.87800+05 5.00000+02          0          0         12          02877 8457   35
 1.00000+00 0.00000+00 5.90000+01 4.20743+00 0.00000+00 0.00000+002877 8457   36
 1.20000-02 0.00000+00 9.32000-03 2.79600-04 2.01000-03 6.03000-052877 8457   37
 1.01180+06 5.00000+02          0          0         12          02877 8457   38
 1.00000+00 0.00000+00 3.60000+00 2.69072-01 0.00000+00 0.00000+002877 8457   39
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002877 8457   40
 0.00000+00 1.00000+00          0          0          6          22877 8457   41
 1.00000-02 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002877 8457   42
 1.78498+05 1.88677+03          0          0          6          02877 8457   43
 1.00000+00 1.00000+00 9.70000+01 3.00000+00 0.00000+00 0.00000+002877 8457   44
 1.93398+05 1.83573+03          0          0          6          02877 8457   45
 1.00000+00 1.00000+00 3.00000+00 3.00000+00 0.00000+00 0.00000+002877 8457   46
 0.00000+00 8.00000+00          0          0          6         302877 8457   47
 1.00000-02 0.00000+00 8.30595+04 1.92931+03 0.00000+00 0.00000+002877 8457   48
 7.24000+03 0.00000+00          0          0          6          02877 8457   49
 1.00000+00 0.00000+00 2.25188+01 1.65527+00 0.00000+00 0.00000+002877 8457   50
 3.33052+04 5.00000+02          0          0          6          02877 8457   51
 1.00000+00 0.00000+00 5.56250+00 4.09513-01 0.00000+00 0.00000+002877 8457   52
 5.10000+04 0.00000+00          0          0          6          02877 8457   53
 1.00000+00 0.00000+00 6.28781-01 2.22067-01 0.00000+00 0.00000+002877 8457   54
 9.78201+04 5.00000+02          0          0          6          02877 8457   55
 1.00000+00 0.00000+00 1.69100+01 1.24492+00 0.00000+00 0.00000+002877 8457   56
 1.08404+05 5.00001+02          0          0          6          02877 8457   57
 1.00000+00 0.00000+00 4.36990+00 3.21713-01 0.00000+00 0.00000+002877 8457   58
 1.10978+05 5.00000+02          0          0          6          02877 8457   59
 1.00000+00 0.00000+00 1.34390+00 9.89383-02 0.00000+00 0.00000+002877 8457   60
 2.50105+05 5.00000+02          0          0          6          02877 8457   61
 1.00000+00 0.00000+00 4.57560+00 3.62903-01 0.00000+00 0.00000+002877 8457   62
 2.60405+05 5.00000+02          0          0          6          02877 8457   63
 1.00000+00 0.00000+00 2.50800+00 2.00251-01 0.00000+00 0.00000+002877 8457   64
 3.12405+05 5.00000+02          0          0          6          02877 8457   65
 1.00000+00 0.00000+00 4.13000-01 3.37179-02 0.00000+00 0.00000+002877 8457   66
 3.14620+05 5.00000+02          0          0          6          02877 8457   67
 1.00000+00 0.00000+00 1.90650+00 1.51210-01 0.00000+00 0.00000+002877 8457   68
 3.24920+05 5.00000+02          0          0          6          02877 8457   69
 1.00000+00 0.00000+00 1.00650+00 8.03639-02 0.00000+00 0.00000+002877 8457   70
 3.25204+05 5.00001+02          0          0          6          02877 8457   71
 1.00000+00 0.00000+00 4.72440-01 3.74705-02 0.00000+00 0.00000+002877 8457   72
 3.27778+05 5.00000+02          0          0          6          02877 8457   73
 1.00000+00 0.00000+00 1.43220-01 1.13592-02 0.00000+00 0.00000+002877 8457   74
 3.35504+05 5.00001+02          0          0          6          02877 8457   75
 1.00000+00 0.00000+00 2.49700-01 1.99373-02 0.00000+00 0.00000+002877 8457   76
 3.38078+05 5.00000+02          0          0          6          02877 8457   77
 1.00000+00 0.00000+00 7.59000-02 6.06023-03 0.00000+00 0.00000+002877 8457   78
 3.76920+05 5.00000+02          0          0          6          02877 8457   79
 1.00000+00 0.00000+00 6.51000-02 5.31485-03 0.00000+00 0.00000+002877 8457   80
 3.87504+05 5.00001+02          0          0          6          02877 8457   81
 1.00000+00 0.00000+00 1.49100-02 1.21727-03 0.00000+00 0.00000+002877 8457   82
 3.90078+05 5.00000+02          0          0          6          02877 8457   83
 1.00000+00 0.00000+00 4.48000-03 3.65753-04 0.00000+00 0.00000+002877 8457   84
 4.04205+05 5.00000+02          0          0          6          02877 8457   85
 1.00000+00 0.00000+00 1.93030+00 1.50229-01 0.00000+00 0.00000+002877 8457   86
 4.68720+05 5.00000+02          0          0          6          02877 8457   87
 1.00000+00 0.00000+00 5.40290-01 4.20491-02 0.00000+00 0.00000+002877 8457   88
 4.79304+05 5.00001+02          0          0          6          02877 8457   89
 1.00000+00 0.00000+00 1.30950-01 1.01914-02 0.00000+00 0.00000+002877 8457   90
 4.81878+05 5.00000+02          0          0          6          02877 8457   91
 1.00000+00 0.00000+00 4.02550-02 3.13292-03 0.00000+00 0.00000+002877 8457   92
 4.84005+05 5.00000+02          0          0          6          02877 8457   93
 1.00000+00 0.00000+00 4.97000-01 4.05757-02 0.00000+00 0.00000+002877 8457   94
 4.84005+05 5.00000+02          0          0          6          02877 8457   95
 1.00000+00 0.00000+00 1.89000-01 1.54302-02 0.00000+00 0.00000+002877 8457   96
 5.22105+05 5.00000+02          0          0          6          02877 8457   97
 1.00000+00 0.00000+00 7.68800-01 5.82531-02 0.00000+00 0.00000+002877 8457   98
 5.48520+05 5.00000+02          0          0          6          02877 8457   99
 1.00000+00 0.00000+00 2.88750-02 2.35739-03 0.00000+00 0.00000+002877 8457  100
 5.48520+05 5.00000+02          0          0          6          02877 8457  101
 1.00000+00 0.00000+00 1.22850-01 1.00296-02 0.00000+00 0.00000+002877 8457  102
 5.86620+05 5.00000+02          0          0          6          02877 8457  103
 1.00000+00 0.00000+00 1.80420-01 1.36707-02 0.00000+00 0.00000+002877 8457  104
 6.09405+05 5.00000+02          0          0          6          02877 8457  105
 1.00000+00 0.00000+00 5.49880-01 4.25419-02 0.00000+00 0.00000+002877 8457  106
 6.73920+05 5.00000+02          0          0          6          02877 8457  107
 1.00000+00 0.00000+00 1.18590-01 9.17481-03 0.00000+00 0.00000+002877 8457  108
 0.00000+00 9.00000+00          0          0          6          42877 8457  109
 1.00000-02 0.00000+00 1.23141+04 3.04644+02 0.00000+00 0.00000+002877 8457  110
 9.44000+03 0.00000+00          0          0          6          02877 8457  111
 1.00000+00 0.00000+00 1.21255+01 1.46901+00 0.00000+00 0.00000+002877 8457  112
 6.51220+04 2.00000+00          0          0          6          02877 8457  113
 1.00000+00 0.00000+00 4.72717+00 1.92346-01 0.00000+00 0.00000+002877 8457  114
 6.68320+04 2.00000+00          0          0          6          02877 8457  115
 1.00000+00 0.00000+00 8.10836+00 3.18611-01 0.00000+00 0.00000+002877 8457  116
 7.57000+04 0.00000+00          0          0          6          02877 8457  117
 1.00000+00 0.00000+00 3.52977+00 1.47967-01 0.00000+00 0.00000+002877 8457  118
                                                                  2877 8  099999
                                                                  2877 0  0    0
                                                                     0 0  0    0
 7.719500+4 1.932910+2         -1          0          2          12878 1451    1
 0.000000+0 1.000000+0          0          0          0          62878 1451    2
 0.000000+0 0.000000+0          0          0          4        3112878 1451    3
 0.000000+0 0.000000+0          0          0         47          22878 1451    4
 77-Ir-195 ENSDF      EVAL-MAY99 CONVERSION OF ENSDF              2878 1451    5
 /ENSDF/              DIST-NOV07                       261107     2878 1451    6
----JEFF-311          MATERIAL 2878                               2878 1451    7
-----RADIOACTIVE DECAY DATA                                       2878 1451    8
------ENDF-6 FORMAT                                               2878 1451    9
******************************************************************2878 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2878 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2878 1451   12
**             Original data taken from:  ENSDF                 **2878 1451   13
******************************************************************2878 1451   14
******************************************************************2878 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2878 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2878 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2878 1451   18
******************************************************************2878 1451   19
195IR DECAY 2.5 H     2                     I(min) = 0.0E+00 %    2878 1451   20
         Ex = 0.0         keV                     1 decay mode(s) 2878 1451   21
                                                                  2878 1451   22
195IR B- DECAY              Q =  1120.0000 keV       1.6000       2878 1451   23
         Branching                100.0000 %         0.0000       2878 1451   24
                         Br*Q =  1120.0000 keV       1.6000       2878 1451   25
                                              0 isomeric state(s) 2878 1451   26
                                                                  2878 1451   27
Individual beta- transitions                                      2878 1451   28
Final level    end point    shape    av.energy        intensity   2878 1451   29
  211.300    908.694   1.603  0    296.000   0.610    4.000 2.000 2878 1451   30
  129.700    990.294   1.601  0    327.140   0.620   57.00010.000 2878 1451   31
   98.850   1021.144   1.601  0    339.010   0.620   26.00014.000 2878 1451   32
    0.000   1119.993   1.600  0    377.560   0.630   13.000 9.000 2878 1451   33
                                                                  2878 1451   34
         Mean alpha    energy       0.0000 keV       0.0000       2878 1451   35
         Mean beta     energy     335.5352 keV      67.1764       2878 1451   36
         Mean conv. e- energy      37.0682 keV       4.2493       2878 1451   37
         Mean Auger e- energy       5.7513 keV       0.9364       2878 1451   38
         Mean gamma    energy      16.7055 keV                    2878 1451   39
         Mean X        energy      41.6835 keV       5.8912       2878 1451   40
         Mean recoil   energy       0.0062 keV       0.0012       2878 1451   41
         Mean neutrino energy     676.3766 keV     134.6582       2878 1451   42
         Mean neutron  energy       0.0000 keV       0.0000       2878 1451   43
         Total         energy    1113.1265 keV     150.6890       2878 1451   44
         Q effective             1120.0000 keV       1.6000       2878 1451   45
         diff. mode                -6.8735 keV      -0.6137 %     2878 1451   46
                                                                  2878 1451   47
         Mean e- bind. energy      53.3626 keV                    2878 1451   48
         diff. atomic              -5.9278 keV     -11.1085 %     2878 1451   49
         diff. nuclear             -0.9457 keV      -0.0844 %     2878 1451   50
                                                                  2878 1451   51
                                1        451         53          02878 1451   52
                                8        457         73          02878 1451   53
 0.000000+0 0.000000+0          0          0          0          02878 1  099999
                                                                  2878 0  0    0
 7.71950+04 1.93291+02          0          0          0          42878 8457    1
 9.00000+03 7.20000+02          0          0          6          02878 8457    2
 3.78355+05 6.73171+04 5.83890+04 6.53734+03 0.00000+00 0.00000+002878 8457    3
 1.50000+00 1.00000+00          0          0          6          12878 8457    4
 1.00000+00 0.00000+00 1.12000+06 1.60000+03 1.00000+00 0.00000+002878 8457    5
 0.00000+00 0.00000+00          0          0          6          42878 8457    6
 1.00000-02 0.00000+00 1.67055+04 2.83390+03 0.00000+00 0.00000+002878 8457    7
 3.08500+04 0.00000+00          0          0         12          02878 8457    8
 1.00000+00 0.00000+00 1.32599+00 3.41750-01 0.00000+00 0.00000+002878 8457    9
 3.95000+01 2.00000-01 0.00000+00 0.00000+00 3.02100+01 9.22106-012878 8457   10
 9.88500+04 5.00000+01          0          0         12          02878 8457   11
 1.00000+00 0.00000+00 9.72910+00 2.50750+00 0.00000+00 0.00000+002878 8457   12
 7.12000+00 0.00000+00 5.79600+00 1.73983-01 1.01730+00 3.06212-022878 8457   13
 1.29700+05 5.00000+01          0          0         12          02878 8457   14
 1.00000+00 0.00000+00 1.24645+00 3.21250-01 0.00000+00 0.00000+002878 8457   15
 1.76000+00 0.00000+00 4.75000-01 1.42500-02 9.61000-01 2.88300-022878 8457   16
 2.11300+05 1.00000+02          0          0         12          02878 8457   17
 1.00000+00 0.00000+00 2.39590+00 6.17500-01 0.00000+00 0.00000+002878 8457   18
 7.62000-01 1.00000-02 6.15000-01 2.09858-02 1.12710-01 3.38154-032878 8457   19
 0.00000+00 1.00000+00          0          0          6          42878 8457   20
 1.00000-02 0.00000+00 3.35535+05 6.71764+04 0.00000+00 0.00000+002878 8457   21
 9.08694+05 1.60311+03          0          0          6          02878 8457   22
 1.00000+00 1.00000+00 4.00000+00 2.00000+00 0.00000+00 0.00000+002878 8457   23
 9.90294+05 1.60077+03          0          0          6          02878 8457   24
 1.00000+00 1.00000+00 5.70000+01 1.00000+01 0.00000+00 0.00000+002878 8457   25
 1.02114+06 1.60077+03          0          0          6          02878 8457   26
 1.00000+00 1.00000+00 2.60000+01 1.40000+01 0.00000+00 0.00000+002878 8457   27
 1.11999+06 1.59999+03          0          0          6          02878 8457   28
 1.00000+00 1.00000+00 1.30000+01 9.00000+00 0.00000+00 0.00000+002878 8457   29
 0.00000+00 8.00000+00          0          0          6         162878 8457   30
 1.00000-02 0.00000+00 4.28195+04 4.35129+03 0.00000+00 0.00000+002878 8457   31
 7.24000+03 0.00000+00          0          0          6          02878 8457   32
 1.00000+00 0.00000+00 6.42020+01 1.11389+01 0.00000+00 0.00000+002878 8457   33
 1.69701+04 0.00000+00          0          0          6          02878 8457   34
 1.00000+00 0.00000+00 4.00582+01 1.03964+01 0.00000+00 0.00000+002878 8457   35
 2.04552+04 5.00049+01          0          0          6          02878 8457   36
 1.00000+00 0.00000+00 5.63899+01 1.46317+01 0.00000+00 0.00000+002878 8457   37
 2.75540+04 0.00000+00          0          0          6          02878 8457   38
 1.00000+00 0.00000+00 9.25541+00 2.40244+00 0.00000+00 0.00000+002878 8457   39
 5.10000+04 0.00000+00          0          0          6          02878 8457   40
 1.00000+00 0.00000+00 2.16285+00 9.33165-01 0.00000+00 0.00000+002878 8457   41
 5.13052+04 5.00049+01          0          0          6          02878 8457   42
 1.00000+00 0.00000+00 5.92064-01 1.53624-01 0.00000+00 0.00000+002878 8457   43
 8.49701+04 5.00016+01          0          0          6          02878 8457   44
 1.00000+00 0.00000+00 9.89741+00 2.56822+00 0.00000+00 0.00000+002878 8457   45
 9.55540+04 5.00081+01          0          0          6          02878 8457   46
 1.00000+00 0.00000+00 2.29704+00 5.96057-01 0.00000+00 0.00000+002878 8457   47
 9.81280+04 5.00036+01          0          0          6          02878 8457   48
 1.00000+00 0.00000+00 7.27445-01 1.88762-01 0.00000+00 0.00000+002878 8457   49
 1.15820+05 5.00016+01          0          0          6          02878 8457   50
 1.00000+00 0.00000+00 1.19784+00 3.10806-01 0.00000+00 0.00000+002878 8457   51
 1.26404+05 5.00081+01          0          0          6          02878 8457   52
 1.00000+00 0.00000+00 3.08122-01 7.99492-02 0.00000+00 0.00000+002878 8457   53
 1.28978+05 5.00036+01          0          0          6          02878 8457   54
 1.00000+00 0.00000+00 9.48548-02 2.46122-02 0.00000+00 0.00000+002878 8457   55
 1.32905+05 1.00002+02          0          0          6          02878 8457   56
 1.00000+00 0.00000+00 1.47348+00 3.83077-01 0.00000+00 0.00000+002878 8457   57
 1.97420+05 1.00001+02          0          0          6          02878 8457   58
 1.00000+00 0.00000+00 2.70042-01 7.00684-02 0.00000+00 0.00000+002878 8457   59
 2.08004+05 1.00004+02          0          0          6          02878 8457   60
 1.00000+00 0.00000+00 6.29882-02 1.63443-02 0.00000+00 0.00000+002878 8457   61
 2.10578+05 1.00002+02          0          0          6          02878 8457   62
 1.00000+00 0.00000+00 1.96703-02 5.10390-03 0.00000+00 0.00000+002878 8457   63
 0.00000+00 9.00000+00          0          0          6          42878 8457   64
 1.00000-02 0.00000+00 4.16835+04 5.89117+03 0.00000+00 0.00000+002878 8457   65
 9.44000+03 0.00000+00          0          0          6          02878 8457   66
 1.00000+00 0.00000+00 3.45703+01 6.85990+00 0.00000+00 0.00000+002878 8457   67
 6.51220+04 2.00000+00          0          0          6          02878 8457   68
 1.00000+00 0.00000+00 1.62603+01 4.08377+00 0.00000+00 0.00000+002878 8457   69
 6.68320+04 2.00000+00          0          0          6          02878 8457   70
 1.00000+00 0.00000+00 2.78907+01 6.99855+00 0.00000+00 0.00000+002878 8457   71
 7.57000+04 0.00000+00          0          0          6          02878 8457   72
 1.00000+00 0.00000+00 1.21415+01 3.05180+00 0.00000+00 0.00000+002878 8457   73
                                                                  2878 8  099999
                                                                  2878 0  0    0
                                                                     0 0  0    0
 7.719500+4 1.932910+2         -1          0          2          12879 1451    1
 1.230000+5 1.000000+0          1          1          0          62879 1451    2
 0.000000+0 0.000000+0          0          0          4        3112879 1451    3
 0.000000+0 0.000000+0          0          0         18          22879 1451    4
 77-Ir-195MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2879 1451    5
                      DIST-NOV07                       261107     2879 1451    6
----JEFF-311          MATERIAL 2879                               2879 1451    7
-----RADIOACTIVE DECAY DATA                                       2879 1451    8
------ENDF-6 FORMAT                                               2879 1451    9
******************************************************************2879 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2879 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2879 1451   12
**             Original data taken from:  NUBASE                **2879 1451   13
******************************************************************2879 1451   14
******************************************************************2879 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2879 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2879 1451   17
                                                                  2879 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2879 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2879 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2879 1451   21
******************************************************************2879 1451   22
                                1        451         24          02879 1451   23
                                8        457          7          02879 1451   24
 0.000000+0 0.000000+0          0          0          0          02879 1  099999
                                                                  2879 0  0    0
 7.71950+04 1.93291+02          1          1          0          02879 8457    1
 1.36800+04 7.20000+02          0          0          6          02879 8457    2
 3.63224+05 0.00000+00 3.69374+05 0.00000+00 0.00000+00 0.00000+002879 8457    3
 5.50000+00-1.00000+00          0          0         18          32879 8457    4
 1.00000+00 0.00000+00 1.23000+06 0.00000+00 6.46000-01 0.00000+002879 8457    5
 1.00000+00 1.00000+00 9.70700+05 0.00000+00 3.04000-01 0.00000+002879 8457    6
 3.00000+00 0.00000+00 1.23000+05 0.00000+00 5.00000-02 0.00000+002879 8457    7
                                                                  2879 8  099999
                                                                  2879 0  0    0
                                                                     0 0  0    0
 7.719600+4 1.942850+2         -1          0          2          12880 1451    1
 0.000000+0 1.000000+0          0          0          0          62880 1451    2
 0.000000+0 0.000000+0          0          0          4        3112880 1451    3
 0.000000+0 0.000000+0          0          0         50          22880 1451    4
 77-Ir-196 ENSDF      EVAL-FEB98 CONVERSION OF ENSDF              2880 1451    5
 /ENSDF/              DIST-NOV07                       261107     2880 1451    6
----JEFF-311          MATERIAL 2880                               2880 1451    7
-----RADIOACTIVE DECAY DATA                                       2880 1451    8
------ENDF-6 FORMAT                                               2880 1451    9
******************************************************************2880 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2880 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2880 1451   12
**             Original data taken from:  ENSDF                 **2880 1451   13
******************************************************************2880 1451   14
******************************************************************2880 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2880 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2880 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2880 1451   18
******************************************************************2880 1451   19
196IR DECAY 52 S      2                     I(min) = 0.0E+00 %    2880 1451   20
         Ex = 0.0         keV                     1 decay mode(s) 2880 1451   21
                                                                  2880 1451   22
196IR B- DECAY              Q =  3209.0000 keV      38.0000       2880 1451   23
         Branching                100.0000 %         0.0000       2880 1451   24
                         Br*Q =  3209.0000 keV      38.0000       2880 1451   25
                                              0 isomeric state(s) 2880 1451   26
                                                                  2880 1451   27
Individual beta- transitions                                      2880 1451   28
Final level    end point    shape    av.energy        intensity   2880 1451   29
 1918.830   1290.147  38.000  0    445.000  16.000    1.200 0.200 2880 1451   30
 1824.100   1384.876  38.001  0    484.000  16.000    0.800 0.100 2880 1451   31
 1402.600   1806.368  38.001  0    658.000  16.000    1.000 0.200 2880 1451   32
 1135.610   2073.354  38.000  0    771.000  17.000   15.000 3.000 2880 1451   33
  689.200   2519.756  38.000  1    937.000  16.000    0.100 0.100 2880 1451   34
  355.650   2853.300  38.000  1   1079.000  17.000    2.200 0.600 2880 1451   35
    0.000   3208.944  37.999  0   1265.000  17.000   80.000 4.000 2880 1451   36
                                                                  2880 1451   37
         Mean alpha    energy       0.0000 keV       0.0000       2880 1451   38
         Mean beta     energy    1168.1170 keV      57.7286       2880 1451   39
         Mean conv. e- energy       0.0000 keV       0.0000       2880 1451   40
         Mean Auger e- energy       0.0000 keV       0.0000       2880 1451   41
         Mean gamma    energy     227.2136 keV                    2880 1451   42
         Mean X        energy       0.0000 keV       0.0000       2880 1451   43
         Mean recoil   energy       0.0525 keV       0.0026       2880 1451   44
         Mean neutrino energy    1819.9577 keV      88.8214       2880 1451   45
         Mean neutron  energy       0.0000 keV       0.0000       2880 1451   46
         Total         energy    3215.3412 keV     108.9978       2880 1451   47
         Q effective             3209.0000 keV      38.0000       2880 1451   48
         diff. mode                 6.3412 keV       0.1976 %     2880 1451   49
                                                                  2880 1451   50
         Mean e- bind. energy       0.0000 keV                    2880 1451   51
         diff. atomic               0.0000 keV       0.0000 %     2880 1451   52
         diff. nuclear              6.3412 keV       0.1976 %     2880 1451   53
                                                                  2880 1451   54
                                1        451         56          02880 1451   55
                                8        457         47          02880 1451   56
 0.000000+0 0.000000+0          0          0          0          02880 1  099999
                                                                  2880 0  0    0
 7.71960+04 1.94285+02          0          0          0          22880 8457    1
 5.20000+01 2.00000+00          0          0          6          02880 8457    2
 1.16812+06 5.77286+04 2.27214+05 2.56649+04 0.00000+00 0.00000+002880 8457    3
 0.00000+00-1.00000+00          0          0          6          12880 8457    4
 1.00000+00 0.00000+00 3.20900+06 3.80000+04 1.00000+00 0.00000+002880 8457    5
 0.00000+00 0.00000+00          0          0          6          82880 8457    6
 1.00000-02 0.00000+00 2.27214+05 2.56649+04 0.00000+00 0.00000+002880 8457    7
 3.32900+05 2.00000+02          0          0         12          02880 8457    8
 1.00000+00 0.00000+00 3.85200+00 8.82832-01 0.00000+00 0.00000+002880 8457    9
 7.90000-02 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002880 8457   10
 3.55700+05 2.00000+02          0          0         12          02880 8457   11
 1.00000+00 0.00000+00 1.80000+01 4.00000+00 0.00000+00 0.00000+002880 8457   12
 6.09000-02 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002880 8457   13
 4.46800+05 2.00000+02          0          0         12          02880 8457   14
 1.00000+00 0.00000+00 5.72400+00 1.29021+00 0.00000+00 0.00000+002880 8457   15
 3.31000-02 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002880 8457   16
 7.79600+05 2.00000+02          0          0         12          02880 8457   17
 1.00000+00 0.00000+00 1.09260+01 2.46304+00 0.00000+00 0.00000+002880 8457   18
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002880 8457   19
 1.04700+06 2.00000+02          0          0         12          02880 8457   20
 1.00000+00 0.00000+00 1.04400+00 2.55906-01 0.00000+00 0.00000+002880 8457   21
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002880 8457   22
 1.22860+06 2.00000+02          0          0         12          02880 8457   23
 1.00000+00 0.00000+00 3.42000-01 1.78941-01 0.00000+00 0.00000+002880 8457   24
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002880 8457   25
 1.46840+06 2.00000+02          0          0         12          02880 8457   26
 1.00000+00 0.00000+00 9.00000-01 3.21720-01 0.00000+00 0.00000+002880 8457   27
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002880 8457   28
 1.56420+06 2.00000+02          0          0         12          02880 8457   29
 1.00000+00 0.00000+00 7.20000-01 2.15258-01 0.00000+00 0.00000+002880 8457   30
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002880 8457   31
 0.00000+00 1.00000+00          0          0          6          72880 8457   32
 1.00000-02 0.00000+00 1.16812+06 5.77286+04 0.00000+00 0.00000+002880 8457   33
 1.29015+06 3.80002+04          0          0          6          02880 8457   34
 1.00000+00 1.00000+00 1.20000+00 2.00000-01 0.00000+00 0.00000+002880 8457   35
 1.38488+06 3.80005+04          0          0          6          02880 8457   36
 1.00000+00 1.00000+00 8.00000-01 1.00000-01 0.00000+00 0.00000+002880 8457   37
 1.80637+06 3.80005+04          0          0          6          02880 8457   38
 1.00000+00 1.00000+00 1.00000+00 2.00000-01 0.00000+00 0.00000+002880 8457   39
 2.07335+06 3.80002+04          0          0          6          02880 8457   40
 1.00000+00 1.00000+00 1.50000+01 3.00000+00 0.00000+00 0.00000+002880 8457   41
 2.51976+06 3.80001+04          0          0          6          02880 8457   42
 1.00000+00 2.00000+00 1.00000-01 1.00000-01 0.00000+00 0.00000+002880 8457   43
 2.85330+06 3.79998+04          0          0          6          02880 8457   44
 1.00000+00 2.00000+00 2.20000+00 6.00000-01 0.00000+00 0.00000+002880 8457   45
 3.20894+06 3.79993+04          0          0          6          02880 8457   46
 1.00000+00 1.00000+00 8.00000+01 4.00000+00 0.00000+00 0.00000+002880 8457   47
                                                                  2880 8  099999
                                                                  2880 0  0    0
                                                                     0 0  0    0
 7.719600+4 1.942850+2         -1          0          2          12881 1451    1
 2.100000+5 1.000000+0          1          1          0          62881 1451    2
 0.000000+0 0.000000+0          0          0          4        3112881 1451    3
 0.000000+0 0.000000+0          0          0         18          22881 1451    4
 77-Ir-196MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2881 1451    5
                      DIST-NOV07                       261107     2881 1451    6
----JEFF-311          MATERIAL 2881                               2881 1451    7
-----RADIOACTIVE DECAY DATA                                       2881 1451    8
------ENDF-6 FORMAT                                               2881 1451    9
******************************************************************2881 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2881 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2881 1451   12
**             Original data taken from:  NUBASE                **2881 1451   13
******************************************************************2881 1451   14
******************************************************************2881 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2881 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2881 1451   17
                                                                  2881 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2881 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2881 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2881 1451   21
******************************************************************2881 1451   22
                                1        451         24          02881 1451   23
                                8        457          6          02881 1451   24
 0.000000+0 0.000000+0          0          0          0          02881 1  099999
                                                                  2881 0  0    0
 7.71960+04 1.94285+02          1          1          0          02881 8457    1
 5.04000+03 7.20000+01          0          0          6          02881 8457    2
 1.13572+06 0.00000+00 1.13635+06 0.00000+00 0.00000+00 0.00000+002881 8457    3
-7.77770+01 0.00000+00          0          0         12          22881 8457    4
 1.00000+00 0.00000+00 3.41740+06 0.00000+00 9.97000-01 0.00000+002881 8457    5
 3.00000+00 0.00000+00 2.10000+05 0.00000+00 3.00000-03 0.00000+002881 8457    6
                                                                  2881 8  099999
                                                                  2881 0  0    0
                                                                     0 0  0    0
 7.719700+4 1.952780+2         -1          0          2          12882 1451    1
 0.000000+0 1.000000+0          0          0          0          62882 1451    2
 0.000000+0 0.000000+0          0          0          4        3112882 1451    3
 0.000000+0 0.000000+0          0          0        117          22882 1451    4
 77-Ir-197 HAR+WIN    EVAL-OCT00 A.L. NICHOLS                     2882 1451    5
                      DIST-NOV07                       261107     2882 1451    6
----JEFF-311          MATERIAL 2882                               2882 1451    7
-----RADIOACTIVE DECAY DATA                                       2882 1451    8
------ENDF-6 FORMAT                                               2882 1451    9
******************************************************************2882 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2882 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2882 1451   12
**             Original data taken from:  UKPADD67              **2882 1451   13
******************************************************************2882 1451   14
                                                                  2882 1451   15
          ZHOU CHUNMEI             NUCL DATA SHEETS 62(1991)433   2882 1451   16
          ZHOU CHUNMEI             NUCL DATA SHEETS 76(1995)399   2882 1451   17
          D CHRISTIAN ET AL        PHYS REV 86(1952)946           2882 1451   18
          F D S BUTEMENT, A J POE  PHIL MAG 45(1954)31            2882 1451   19
          S HOMMA ET AL            J PHYS SOC JAPAN 16(1961)841   2882 1451   20
          S C ALVES ET AL          Z NATURFORSCH 29A(1974)1917    2882 1451   21
          J C HILL ET AL           CERN-76-13(1976)532            2882 1451   22
          R F PETRY ET AL          BULL AMER PHYS SOC             2882 1451   23
                                   21(1976)558, DG4               2882 1451   24
          R F PETRY ET AL          BULL AMER PHYS SOC             2882 1451   25
                                   23(1978)945, DD7               2882 1451   26
                                                                  2882 1451   27
 The half-life of 5.8(5) min was assigned by Petry et al (1978),  2882 1451   28
who also attributed approximately 100 observed gamma rays to the  2882 1451   29
decay of Ir-197; this half-life is in disagreement with a value   2882 1451   30
of 10(1) min quoted by Hill et al.  Spin and parity analyses of   2882 1451   31
the beta decay imply that the vast majority of these gamma rays   2882 1451   32
can be attributed to the beta decay of Ir-197g (rather than       2882 1451   33
Ir-197m).  Unfortunately, the gamma-ray emissions have not been   2882 1451   34
reported in a quantitative manner; the only available gamma-ray   2882 1451   35
data are relative emission probabilities for 33 gamma rays, as    2882 1451   36
listed by Hill et al (relative to 100% for the 470 keV gamma      2882 1451   37
ray) without any uncertainty assignments.                         2882 1451   38
                                                                  2882 1451   39
 A respectable decay scheme is difficult to derive from the       2882 1451   40
sparse and inadequate data sets.  Minor adjustments were made to  2882 1451   41
the energies of the gamma-ray transitions reported by Hill et     2882 1451   42
al, and a number of unobserved emissions were introduced to       2882 1451   43
produce a rather subjective yet complete decay scheme (71.6,      2882 1451   44
131.0, 138.1, 216.0, 403.8, 439.3 and 636.8 keV gamma rays).      2882 1451   45
Furthermore, the relative emission probabilities of the 534 and   2882 1451   46
539 keV gamma rays were modified to achieve the desired           2882 1451   47
population/depopulation balance of specific nuclear levels.  The  2882 1451   48
resulting decay scheme contains only 40 gamma-ray transitions     2882 1451   49
(rather than 100, as quoted by Petry et al (1978)).  Some of the  2882 1451   50
nuclear levels proposed by Alves et al were also adopted, in      2882 1451   51
conjunction with the gamma-ray data of Hill et al.                2882 1451   52
                                                                  2882 1451   53
 A normalisation factor for the relative emission probabilities   2882 1451   54
of the gamma rays proved difficult to derive.  Rather             2882 1451   55
arbitrarily, the evaluator assumed equal beta-particle emission   2882 1451   56
probabilities to the ground and 53.08 keV nuclear levels of Pt-   2882 1451   57
197.  This approach resulted in a normalisation factor of 0.067,  2882 1451   58
but places considerable emphasis on the relative emission         2882 1451   59
probability of the 53.1 keV gamma ray as measured by Hill et al   2882 1451   60
(8.8%).  No uncertainties had been assigned to the relative       2882 1451   61
emission probabilities of the gamma rays, and they were           2882 1451   62
estimated as ranging between 5 and 20% by the evaluator.  A       2882 1451   63
large number of these transitions were mixed M1 + E2              2882 1451   64
multipolarity; apart from the 71.6 keV gamma-ray transition, all  2882 1451   65
such emissions were assigned theoretical internal conversion      2882 1451   66
coefficients corresponding to 50%M1 + 50%E2.                      2882 1451   67
                                                                  2882 1451   68
 The beta-particle transitions were calculated from the sparse    2882 1451   69
gamma-ray data and postulated decay scheme.  These primary        2882 1451   70
transitions are more detailed than merited by the quality of the  2882 1451   71
available data, with almost all the beta-particle emissions       2882 1451   72
assumed to be first forbidden non-unique.                         2882 1451   73
                                                                  2882 1451   74
 The proposed decay scheme is highly questionable and extremely   2882 1451   75
uncertain.  Some of the postulated nuclear levels are dubious,    2882 1451   76
despite the apparent completeness of the resulting data set.      2882 1451   77
Gamma-ray measurements are required in order to develop a         2882 1451   78
reliable decay scheme with considerably more confidence,          2882 1451   79
although difficulties are envisaged in differentiating between    2882 1451   80
the decay of Ir-197g and Ir-197m.                                 2882 1451   81
                                                                  2882 1451   82
                                                                  2882 1451   83
      MEAN BETA- ENERGIES:-                                       2882 1451   84
   END POINT(MEV)= 0.6740  SHAPE= 1  MEAN= 0.2092  INT= 0.0110    2882 1451   85
   END POINT(MEV)= 0.8120  SHAPE= 1  MEAN= 0.2594  INT= 0.0140    2882 1451   86
   END POINT(MEV)= 0.8470  SHAPE= 1  MEAN= 0.2724  INT= 0.0100    2882 1451   87
   END POINT(MEV)= 0.8560  SHAPE= 1  MEAN= 0.2758  INT= 0.0300    2882 1451   88
   END POINT(MEV)= 0.8830  SHAPE= 1  MEAN= 0.2859  INT= 0.0031    2882 1451   89
   END POINT(MEV)= 0.9090  SHAPE= 1  MEAN= 0.2957  INT= 0.0013    2882 1451   90
   END POINT(MEV)= 1.1470  SHAPE= 1  MEAN= 0.3876  INT= 0.0019    2882 1451   91
   END POINT(MEV)= 1.2160  SHAPE= 1  MEAN= 0.4148  INT= 0.0065    2882 1451   92
   END POINT(MEV)= 1.2820  SHAPE= 1  MEAN= 0.4412  INT= 0.0043    2882 1451   93
   END POINT(MEV)= 1.2920  SHAPE= 1  MEAN= 0.4452  INT= 0.0250    2882 1451   94
   END POINT(MEV)= 1.3050  SHAPE= 1  MEAN= 0.4504  INT= 0.0068    2882 1451   95
   END POINT(MEV)= 1.3590  SHAPE= 1  MEAN= 0.4722  INT= 0.0200    2882 1451   96
   END POINT(MEV)= 1.4470  SHAPE= 1  MEAN= 0.5079  INT= 0.0016    2882 1451   97
   END POINT(MEV)= 1.6050  SHAPE= 1  MEAN= 0.5728  INT= 0.0260    2882 1451   98
   END POINT(MEV)= 1.6320  SHAPE= 1  MEAN= 0.5840  INT= 0.0710    2882 1451   99
   END POINT(MEV)= 1.6710  SHAPE= 2  MEAN= 0.5828  INT= 0.0140    2882 1451  100
   END POINT(MEV)= 1.6980  SHAPE= 1  MEAN= 0.6114  INT= 0.0270    2882 1451  101
   END POINT(MEV)= 1.7760  SHAPE= 1  MEAN= 0.6440  INT= 0.0280    2882 1451  102
   END POINT(MEV)= 1.8560  SHAPE= 1  MEAN= 0.6776  INT= 0.0220    2882 1451  103
   END POINT(MEV)= 1.8860  SHAPE= 1  MEAN= 0.6902  INT= 0.0015    2882 1451  104
   END POINT(MEV)= 1.9360  SHAPE= 1  MEAN= 0.7113  INT= 0.0170    2882 1451  105
   END POINT(MEV)= 2.1020  SHAPE= 1  MEAN= 0.7818  INT= 0.3300    2882 1451  106
   END POINT(MEV)= 2.1550  SHAPE= 1  MEAN= 0.8044  INT= 0.3300    2882 1451  107
                                                                  2882 1451  108
      MEAN GAMMA ENERGY              =    217.8930  KEV           2882 1451  109
      MEAN BETA- ENERGY              =    696.4226  KEV           2882 1451  110
      BETA- + NEUTRINO ENERGY        =   1901.0691  KEV           2882 1451  111
      MEAN X-RAY ENERGY              =      3.7974  KEV           2882 1451  112
      MEAN AUGER ELECTRON ENERGY     =      3.9521  KEV           2882 1451  113
      MEAN CONVERSION ELECTRON ENERGY=     32.9937  KEV           2882 1451  114
      INTERNAL BREMSSTRAHLUNG ENERGY =      2.1020  KEV           2882 1451  115
      EFFECTIVE Q VALUE              =   2155.0000  KEV           2882 1451  116
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.9281                2882 1451  117
      CALCULATED Q VALUE             =   2159.7056  KEV           2882 1451  118
      % DEVIATION                    =     -0.2184                2882 1451  119
                                                                  2882 1451  120
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2882 1451  121
                                1        451        123          12882 1451  122
                                8        457        373          12882 1451  123
 0.000000+0 0.000000+0          0          0          0          02882 1  099999
                                                                  2882 0  0    0
7.71970E+041.95278E+02          0          0          0          42882 8457    1
3.48000E+023.00000E+01          0          0          6          02882 8457    2
7.33368E+057.79756E+042.23792E+052.95487E+040.00000E+000.00000E+002882 8457    3
1.50000E+00 1.0000E+00          0          0          6          12882 8457    4
1.00000E+000.00000E+002.15500E+062.00000E+041.00000E+000.00000E+002882 8457    5
0.00000E+000.00000E+00          0          0          6         402882 8457    6
6.70000E-029.00000E-032.17893E+052.95455E+040.00000E+000.00000E+002882 8457    7
5.31000E+041.00000E+02          0          0         12          02882 8457    8
1.00000E+000.00000E+008.80000E-029.00000E-030.00000E+000.00000E+002882 8457    9
8.85000E+018.85000E-010.00000E+000.00000E+006.63000E+016.63000E-012882 8457   10
7.16000E+041.00000E+02          0          0         12          02882 8457   11
1.00000E+000.00000E+002.00000E-021.00000E-020.00000E+000.00000E+002882 8457   12
3.60000E+003.99600E-010.00000E+000.00000E+002.80000E+003.10800E-012882 8457   13
1.31000E+051.00000E+02          0          0         12          02882 8457   14
1.00000E+000.00000E+003.40000E-021.00000E-020.00000E+000.00000E+002882 8457   15
2.50000E+003.00000E-011.60000E+001.92000E-017.00000E-018.40000E-022882 8457   16
1.38100E+051.00000E+02          0          0         12          02882 8457   17
1.00000E+000.00000E+004.00000E-021.00000E-020.00000E+000.00000E+002882 8457   18
2.08000E+001.99680E-011.35000E+001.29600E-015.50000E-015.28000E-022882 8457   19
1.57600E+051.00000E+02          0          0         12          02882 8457   20
1.00000E+000.00000E+004.00000E-025.00000E-030.00000E+000.00000E+002882 8457   21
1.38000E+001.39380E-019.40000E-019.49400E-023.30000E-013.33300E-022882 8457   22
1.66100E+055.00000E+02          0          0         12          02882 8457   23
1.00000E+000.00000E+001.20000E-012.00000E-020.00000E+000.00000E+002882 8457   24
1.17000E+001.20510E-018.10000E-018.34300E-022.70000E-012.78100E-022882 8457   25
2.16000E+051.00000E+02          0          0         12          02882 8457   26
1.00000E+000.00000E+002.50000E-021.00000E-020.00000E+000.00000E+002882 8457   27
5.40000E-015.02200E-024.00000E-013.72000E-021.10000E-011.02300E-022882 8457   28
2.27700E+051.00000E+02          0          0         12          02882 8457   29
1.00000E+000.00000E+002.40000E-028.00000E-030.00000E+000.00000E+002882 8457   30
4.60000E-015.01400E-023.40000E-013.70600E-029.00000E-029.81000E-032882 8457   31
2.46300E+051.00000E+02          0          0         12          02882 8457   32
1.00000E+000.00000E+008.40000E-029.00000E-030.00000E+000.00000E+002882 8457   33
3.70000E-013.99600E-022.80000E-013.02400E-027.00000E-027.56000E-032882 8457   34
2.69100E+051.00000E+02          0          0         12          02882 8457   35
1.00000E+000.00000E+001.32000E-019.00000E-030.00000E+000.00000E+002882 8457   36
2.80000E-012.99600E-022.20000E-012.35400E-025.00000E-025.35000E-032882 8457   37
2.99300E+051.00000E+02          0          0         12          02882 8457   38
1.00000E+000.00000E+002.44000E-013.20000E-020.00000E+000.00000E+002882 8457   39
1.00000E-011.00000E-036.20000E-026.20000E-042.90000E-022.90000E-042882 8457   40
3.12000E+051.00000E+03          0          0         12          02882 8457   41
1.00000E+000.00000E+004.40000E-025.00000E-030.00000E+000.00000E+002882 8457   42
1.90000E-011.99500E-021.50000E-011.57500E-023.00000E-023.15000E-032882 8457   43
3.39000E+051.00000E+03          0          0         12          02882 8457   44
1.00000E+000.00000E+004.80000E-025.00000E-030.00000E+000.00000E+002882 8457   45
1.50000E-011.99500E-021.20000E-011.59600E-022.50000E-023.32500E-032882 8457   46
3.78700E+055.00000E+02          0          0         12          02882 8457   47
1.00000E+000.00000E+003.77000E-013.80000E-020.00000E+000.00000E+002882 8457   48
1.10000E-011.00100E-028.80000E-028.00800E-031.80000E-021.63800E-032882 8457   49
4.03800E+051.00000E+02          0          0         12          02882 8457   50
1.00000E+000.00000E+003.00000E-021.00000E-020.00000E+000.00000E+002882 8457   51
9.40000E-029.02400E-037.50000E-027.20000E-031.50000E-021.44000E-032882 8457   52
4.30600E+055.00000E+02          0          0         12          02882 8457   53
1.00000E+000.00000E+006.11000E-013.50000E-020.00000E+000.00000E+002882 8457   54
7.90000E-027.97900E-036.30000E-026.36300E-031.20000E-021.21200E-032882 8457   55
4.39300E+051.00000E+02          0          0         12          02882 8457   56
1.00000E+000.00000E+001.00000E-022.00000E-030.00000E+000.00000E+002882 8457   57
7.50000E-028.02500E-036.00000E-026.42000E-031.10000E-021.17700E-032882 8457   58
4.56900E+051.00000E+02          0          0         12          02882 8457   59
1.00000E+000.00000E+003.71000E-013.30000E-020.00000E+000.00000E+002882 8457   60
3.13000E-023.13000E-042.25000E-022.25000E-046.70000E-036.70000E-052882 8457   61
4.70000E+051.00000E+03          0          0         12          02882 8457   62
1.00000E+000.00000E+001.00000E+000.00000E+000.00000E+000.00000E+002882 8457   63
6.20000E-026.01400E-035.00000E-024.85000E-039.50000E-039.21500E-042882 8457   64
4.97000E+051.00000E+03          0          0         12          02882 8457   65
1.00000E+000.00000E+003.62000E-013.20000E-020.00000E+000.00000E+002882 8457   66
5.40000E-025.02200E-034.40000E-024.09200E-038.10000E-037.53300E-042882 8457   67
5.27000E+051.00000E+03          0          0         12          02882 8457   68
1.00000E+000.00000E+002.38000E-011.40000E-020.00000E+000.00000E+002882 8457   69
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4.85605E+052.42803E+04          0          0          6          02882 8457  306
1.00000E+000.00000E+009.43360E-059.43360E-060.00000E+000.00000E+002882 8457  307
4.94342E+052.47171E+04          0          0          6          02882 8457  308
1.00000E+000.00000E+004.60826E-054.60826E-060.00000E+000.00000E+002882 8457  309
5.02305E+052.51153E+04          0          0          6          02882 8457  310
1.00000E+000.00000E+007.23600E-057.23600E-060.00000E+000.00000E+002882 8457  311
5.15436E+052.57718E+04          0          0          6          02882 8457  312
1.00000E+000.00000E+001.10027E-041.10027E-050.00000E+000.00000E+002882 8457  313
5.22436E+052.61218E+04          0          0          6          02882 8457  314
1.00000E+000.00000E+002.47632E-052.47632E-060.00000E+000.00000E+002882 8457  315
5.24342E+052.62171E+04          0          0          6          02882 8457  316
1.00000E+000.00000E+002.87028E-052.87028E-060.00000E+000.00000E+002882 8457  317
5.27436E+052.63718E+04          0          0          6          02882 8457  318
1.00000E+000.00000E+006.09700E-056.09700E-060.00000E+000.00000E+002882 8457  319
5.30436E+052.65218E+04          0          0          6          02882 8457  320
1.00000E+000.00000E+004.50240E-054.50240E-060.00000E+000.00000E+002882 8457  321
5.31342E+052.65671E+04          0          0          6          02882 8457  322
1.00000E+000.00000E+006.00320E-066.00320E-070.00000E+000.00000E+002882 8457  323
5.36342E+052.68171E+04          0          0          6          02882 8457  324
1.00000E+000.00000E+001.40700E-051.40700E-060.00000E+000.00000E+002882 8457  325
5.39342E+052.69671E+04          0          0          6          02882 8457  326
1.00000E+000.00000E+001.05525E-051.05525E-060.00000E+000.00000E+002882 8457  327
5.52436E+052.76218E+04          0          0          6          02882 8457  328
1.00000E+000.00000E+001.68036E-051.68036E-060.00000E+000.00000E+002882 8457  329
5.58405E+052.79203E+04          0          0          6          02882 8457  330
1.00000E+000.00000E+001.44720E-051.44720E-060.00000E+000.00000E+002882 8457  331
5.61342E+052.80671E+04          0          0          6          02882 8457  332
1.00000E+000.00000E+003.83240E-063.83240E-070.00000E+000.00000E+002882 8457  333
5.69136E+052.84568E+04          0          0          6          02882 8457  334
1.00000E+000.00000E+001.27836E-051.27836E-060.00000E+000.00000E+002882 8457  335
5.78042E+052.89021E+04          0          0          6          02882 8457  336
1.00000E+000.00000E+002.89440E-062.89440E-070.00000E+000.00000E+002882 8457  337
6.25236E+053.12618E+04          0          0          6          02882 8457  338
1.00000E+000.00000E+002.47230E-062.47230E-070.00000E+000.00000E+002882 8457  339
6.30005E+053.15003E+04          0          0          6          02882 8457  340
1.00000E+000.00000E+006.03000E-056.03000E-060.00000E+000.00000E+002882 8457  341
6.34142E+053.17071E+04          0          0          6          02882 8457  342
1.00000E+000.00000E+005.42700E-075.42700E-080.00000E+000.00000E+002882 8457  343
6.37605E+053.18803E+04          0          0          6          02882 8457  344
1.00000E+000.00000E+001.09746E-041.09746E-050.00000E+000.00000E+002882 8457  345
6.60405E+053.30203E+04          0          0          6          02882 8457  346
1.00000E+000.00000E+001.17920E-051.17920E-060.00000E+000.00000E+002882 8457  347
6.96836E+053.48418E+04          0          0          6          02882 8457  348
1.00000E+000.00000E+001.03850E-051.03850E-060.00000E+000.00000E+002882 8457  349
7.04436E+053.52218E+04          0          0          6          02882 8457  350
1.00000E+000.00000E+001.89007E-051.89007E-060.00000E+000.00000E+002882 8457  351
7.05742E+053.52871E+04          0          0          6          02882 8457  352
1.00000E+000.00000E+003.01500E-063.01500E-070.00000E+000.00000E+002882 8457  353
7.13342E+053.56671E+04          0          0          6          02882 8457  354
1.00000E+000.00000E+005.48730E-065.48730E-070.00000E+000.00000E+002882 8457  355
7.27236E+053.63618E+04          0          0          6          02882 8457  356
1.00000E+000.00000E+002.28470E-062.28470E-070.00000E+000.00000E+002882 8457  357
7.36142E+053.68071E+04          0          0          6          02882 8457  358
1.00000E+000.00000E+006.63300E-076.63300E-080.00000E+000.00000E+002882 8457  359
0.00000E+009.00000E+00          0          0          6          62882 8457  360
1.00000E+000.00000E+003.79741E+033.79741E+020.00000E+000.00000E+002882 8457  361
2.65800E+035.31600E+01          0          0          6          02882 8457  362
1.00000E+000.00000E+001.60266E-021.60266E-030.00000E+000.00000E+002882 8457  363
9.69500E+031.93900E+02          0          0          6          02882 8457  364
1.00000E+000.00000E+001.52832E-011.52832E-020.00000E+000.00000E+002882 8457  365
6.51220E+041.30244E+03          0          0          6          02882 8457  366
1.00000E+000.00000E+009.60807E-039.60807E-040.00000E+000.00000E+002882 8457  367
6.68320E+041.33664E+03          0          0          6          02882 8457  368
1.00000E+000.00000E+001.64804E-021.64804E-030.00000E+000.00000E+002882 8457  369
7.57000E+041.51400E+03          0          0          6          02882 8457  370
1.00000E+000.00000E+005.66926E-035.66926E-040.00000E+000.00000E+002882 8457  371
7.79000E+041.55800E+03          0          0          6          02882 8457  372
1.00000E+000.00000E+001.49972E-031.49972E-040.00000E+000.00000E+002882 8457  373
                                                                  2882 8  099999
                                                                  2882 0  0    0
                                                                     0 0  0    0
 7.719700+4 1.952780+2         -1          0          2          12883 1451    1
 1.150000+5 1.000000+0          2          1          0          62883 1451    2
 0.000000+0 0.000000+0          0          0          4        3112883 1451    3
 0.000000+0 0.000000+0          0          0         56          22883 1451    4
 77-Ir-197MHAR+WIN    EVAL-OCT00 A.L. NICHOLS                     2883 1451    5
                      DIST-NOV07                       261107     2883 1451    6
----JEFF-311          MATERIAL 2883                               2883 1451    7
-----RADIOACTIVE DECAY DATA                                       2883 1451    8
------ENDF-6 FORMAT                                               2883 1451    9
******************************************************************2883 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2883 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2883 1451   12
**             Original data taken from:  UKPADD67              **2883 1451   13
******************************************************************2883 1451   14
                                                                  2883 1451   15
          ZHOU CHUNMEI      NUCL DATA SHEETS 62(1991)433          2883 1451   16
          ZHOU CHUNMEI      NUCL DATA SHEETS 76(1995)399          2883 1451   17
          S C ALVES ET AL   Z NATURFORSCH 29A(1974)1917           2883 1451   18
          J C HILL ET AL    CERN-76-13(1976)532                   2883 1451   19
          R F PETRY ET AL   BULL AMER PHYS SOC 21(1976)558, DG4   2883 1451   20
          R F PETRY ET AL   BULL AMER PHYS SOC 23(1978)945, DD7   2883 1451   21
                                                                  2883 1451   22
 A simple decay scheme can be constructed that consists of a      2883 1451   23
single beta transition to Pt-197m and a low-intensity isomeric    2883 1451   24
transition to Ir-197g.  The first forbidden non-unique beta       2883 1451   25
transition from Ir-197m (11/2-) to Pt-197m (13/2+) would appear   2883 1451   26
to be the only such emission; other beta transitions would be     2883 1451   27
highly forbidden, and have been rejected.                         2883 1451   28
                                                                  2883 1451   29
 A single 115 keV gamma-ray transition has been proposed for the  2883 1451   30
IT decay, with high M4 multipolarity (appropriate theoretical     2883 1451   31
internal conversion coefficients were adopted).  These            2883 1451   32
assignments resulted in a very low-intensity gamma-ray emission.  2883 1451   33
                                                                  2883 1451   34
 The half-life of 8.9(3) min was assigned by Petry et al (1978),  2883 1451   35
who also attributed approximately 100 gamma rays to the decay of  2883 1451   36
Ir-197 (assumed to be the decay of Ir-197g).  Further studies are 2883 1451   37
required to understand and resolve the decay parameters of both   2883 1451   38
Ir-197g and Ir-197m, and the detailed gamma-ray decay of both     2883 1451   39
radionuclides.  The beta and IT branching fractions were          2883 1451   40
determined from consideration of the IT transition; the half-life 2883 1451   41
and these branching factors of Ir-197m need to be confirmed.      2883 1451   42
                                                                  2883 1451   43
                                                                  2883 1451   44
      MEAN BETA- ENERGIES:-                                       2883 1451   45
   END POINT(MEV)= 1.8700  SHAPE= 1  MEAN= 0.6835  INT= 0.9975    2883 1451   46
                                                                  2883 1451   47
      MEAN GAMMA ENERGY              =      0.0001  KEV           2883 1451   48
      MEAN BETA- ENERGY              =    679.7504  KEV           2883 1451   49
      BETA- + NEUTRINO ENERGY        =   1865.3250  KEV           2883 1451   50
      MEAN X-RAY ENERGY              =      0.0204  KEV           2883 1451   51
      MEAN AUGER ELECTRON ENERGY     =      0.0161  KEV           2883 1451   52
      MEAN CONVERSION ELECTRON ENERGY=      0.2429  KEV           2883 1451   53
      INTERNAL BREMSSTRAHLUNG ENERGY =      2.0219  KEV           2883 1451   54
      EFFECTIVE Q VALUE              =   1865.6125  KEV           2883 1451   55
      UNCERTAINTY IN EFFECTIVE Q (%) =      1.3405                2883 1451   56
      CALCULATED Q VALUE             =   1865.6045  KEV           2883 1451   57
      % DEVIATION                    =      0.0004                2883 1451   58
                                                                  2883 1451   59
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2883 1451   60
                                1        451         62          12883 1451   61
                                8        457         43          12883 1451   62
 0.000000+0 0.000000+0          0          0          0          02883 1  099999
                                                                  2883 0  0    0
7.71970E+041.95278E+02          2          1          0          42883 8457    1
5.34000E+021.80000E+01          0          0          6          02883 8457    2
6.80009E+059.14023E+032.04244E+032.02202E+020.00000E+000.00000E+002883 8457    3
5.50000E+00-1.0000E+00          0          0         12          22883 8457    4
1.00000E+001.00000E+001.87000E+062.50000E+049.97500E-011.00000E-032883 8457    5
3.00000E+000.00000E+001.15000E+055.00000E+032.50000E-031.00000E-032883 8457    6
0.00000E+000.00000E+00          0          0          6          12883 8457    7
1.10000E-060.00000E+001.26500E-014.63276E-020.00000E+000.00000E+002883 8457    8
1.15000E+055.00000E+03          0          0         12          02883 8457    9
3.00000E+000.00000E+001.00000E+003.63636E-010.00000E+000.00000E+002883 8457   10
2.20900E+032.20900E+012.09000E+022.09000E+001.40800E+031.40800E+012883 8457   11
0.00000E+001.00000E+00          0          0          6          12883 8457   12
1.00000E+000.00000E+006.79750E+059.14019E+030.00000E+000.00000E+002883 8457   13
1.87000E+062.50000E+04          0          0          6          02883 8457   14
1.00000E+001.00000E+009.97500E-011.00000E-030.00000E+000.00000E+002883 8457   15
0.00000E+008.00000E+00          0          0          6          62883 8457   16
1.00000E+000.00000E+002.58996E+022.58996E+010.00000E+000.00000E+002883 8457   17
2.55800E+031.27900E+02          0          0          6          02883 8457   18
3.00000E+000.00000E+002.93842E-032.93842E-040.00000E+000.00000E+002883 8457   19
7.05900E+033.52950E+02          0          0          6          02883 8457   20
3.00000E+000.00000E+001.14572E-031.14572E-040.00000E+000.00000E+002883 8457   21
3.88890E+041.94445E+03          0          0          6          02883 8457   22
3.00000E+000.00000E+002.29900E-042.29900E-050.00000E+000.00000E+002883 8457   23
5.58050E+042.79025E+03          0          0          6          02883 8457   24
3.00000E+000.00000E+008.73620E-068.73620E-070.00000E+000.00000E+002883 8457   25
1.03785E+055.18924E+03          0          0          6          02883 8457   26
3.00000E+000.00000E+001.54880E-031.54880E-040.00000E+000.00000E+002883 8457   27
1.12442E+055.62210E+03          0          0          6          02883 8457   28
3.00000E+000.00000E+006.51200E-046.51200E-050.00000E+000.00000E+002883 8457   29
0.00000E+009.00000E+00          0          0          6          62883 8457   30
1.00000E+000.00000E+002.03899E+012.03899E+000.00000E+000.00000E+002883 8457   31
2.55800E+035.11600E+01          0          0          6          02883 8457   32
3.00000E+000.00000E+005.99678E-055.99678E-060.00000E+000.00000E+002883 8457   33
9.41500E+031.88300E+02          0          0          6          02883 8457   34
3.00000E+000.00000E+005.90219E-045.90219E-050.00000E+000.00000E+002883 8457   35
6.32870E+041.26574E+03          0          0          6          02883 8457   36
3.00000E+000.00000E+006.38015E-056.38015E-060.00000E+000.00000E+002883 8457   37
6.48960E+041.29792E+03          0          0          6          02883 8457   38
3.00000E+000.00000E+001.09813E-041.09813E-050.00000E+000.00000E+002883 8457   39
7.35000E+041.47000E+03          0          0          6          02883 8457   40
3.00000E+000.00000E+003.77757E-053.77757E-060.00000E+000.00000E+002883 8457   41
7.56000E+041.51200E+03          0          0          6          02883 8457   42
3.00000E+000.00000E+009.77338E-069.77338E-070.00000E+000.00000E+002883 8457   43
                                                                  2883 8  099999
                                                                  2883 0  0    0
                                                                     0 0  0    0
 7.719800+4 1.962720+2         -1          0          2          12884 1451    1
 0.000000+0 1.000000+0          0          0          0          62884 1451    2
 0.000000+0 0.000000+0          0          0          4        3112884 1451    3
 0.000000+0 0.000000+0          0          0         18          22884 1451    4
 77-Ir-198 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2884 1451    5
                      DIST-NOV07                       261107     2884 1451    6
----JEFF-311          MATERIAL 2884                               2884 1451    7
-----RADIOACTIVE DECAY DATA                                       2884 1451    8
------ENDF-6 FORMAT                                               2884 1451    9
******************************************************************2884 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2884 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2884 1451   12
**             Original data taken from:  NUBASE                **2884 1451   13
******************************************************************2884 1451   14
******************************************************************2884 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2884 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2884 1451   17
                                                                  2884 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2884 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2884 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2884 1451   21
******************************************************************2884 1451   22
                                1        451         24          02884 1451   23
                                8        457          5          02884 1451   24
 0.000000+0 0.000000+0          0          0          0          02884 1  099999
                                                                  2884 0  0    0
 7.71980+04 1.96272+02          0          0          0          02884 8457    1
 8.00000+00 1.00000+00          0          0          6          02884 8457    2
 1.36267+06 0.00000+00 1.36267+06 0.00000+00 0.00000+00 0.00000+002884 8457    3
-7.77770+01 0.00000+00          0          0          6          12884 8457    4
 1.00000+00 0.00000+00 4.08800+06 0.00000+00 1.00000+00 0.00000+002884 8457    5
                                                                  2884 8  099999
                                                                  2884 0  0    0
                                                                     0 0  0    0
 7.719900+4 1.972650+2         -1          0          2          12885 1451    1
 0.000000+0 1.000000+0          0          0          0          62885 1451    2
 0.000000+0 0.000000+0          0          0          4        3112885 1451    3
 0.000000+0 0.000000+0          0          0         18          22885 1451    4
 77-Ir-199 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2885 1451    5
                      DIST-NOV07                       261107     2885 1451    6
----JEFF-311          MATERIAL 2885                               2885 1451    7
-----RADIOACTIVE DECAY DATA                                       2885 1451    8
------ENDF-6 FORMAT                                               2885 1451    9
******************************************************************2885 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2885 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2885 1451   12
**             Original data taken from:  NUBASE                **2885 1451   13
******************************************************************2885 1451   14
******************************************************************2885 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2885 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2885 1451   17
                                                                  2885 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2885 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2885 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2885 1451   21
******************************************************************2885 1451   22
                                1        451         24          02885 1451   23
                                8        457          5          02885 1451   24
 0.000000+0 0.000000+0          0          0          0          02885 1  099999
                                                                  2885 0  0    0
 7.71990+04 1.97265+02          0          0          0          02885 8457    1
 2.00000+01 0.00000+00          0          0          6          02885 8457    2
 9.97334+05 0.00000+00 9.97334+05 0.00000+00 0.00000+00 0.00000+002885 8457    3
 1.50000+00 1.00000+00          0          0          6          12885 8457    4
 1.00000+00 0.00000+00 2.99200+06 0.00000+00 1.00000+00 0.00000+002885 8457    5
                                                                  2885 8  099999
                                                                  2885 0  0    0
                                                                     0 0  0    0
