 2.203800+4 3.768320+1         -1          0          2          1 402 1451    1
 0.000000+0 1.000000+0          0          0          0          6 402 1451    2
 0.000000+0 0.000000+0          0          0          4        311 402 1451    3
 0.000000+0 0.000000+0          0          0         18          2 402 1451    4
 22-Ti- 38 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  402 1451    5
                      DIST-NOV07                       261107      402 1451    6
----JEFF-311          MATERIAL  402                                402 1451    7
-----RADIOACTIVE DECAY DATA                                        402 1451    8
------ENDF-6 FORMAT                                                402 1451    9
****************************************************************** 402 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 402 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 402 1451   12
**             Original data taken from:  NUBASE                ** 402 1451   13
****************************************************************** 402 1451   14
****************************************************************** 402 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 402 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      402 1451   17
                                                                   402 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           402 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        402 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               402 1451   21
****************************************************************** 402 1451   22
                                1        451         24          0 402 1451   23
                                8        457          5          0 402 1451   24
 0.000000+0 0.000000+0          0          0          0          0 402 1  099999
                                                                   402 0  0    0
 2.20380+04 3.76832+01          0          0          0          0 402 8457    1
 1.20000-07 0.00000+00          0          0          6          0 402 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 9.62001+05 0.00000+00 402 8457    3
 0.00000+00 1.00000+00          0          0          6          1 402 8457    4
 7.70000+00 0.00000+00 9.62001+05 0.00000+00 1.00000+00 0.00000+00 402 8457    5
                                                                   402 8  099999
                                                                   402 0  0    0
                                                                     0 0  0    0
 2.203900+4 3.866660+1         -1          0          2          1 403 1451    1
 0.000000+0 1.000000+0          0          0          0          6 403 1451    2
 0.000000+0 0.000000+0          0          0          4        311 403 1451    3
 0.000000+0 0.000000+0          0          0         18          2 403 1451    4
 22-Ti- 39 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  403 1451    5
                      DIST-NOV07                       261107      403 1451    6
----JEFF-311          MATERIAL  403                                403 1451    7
-----RADIOACTIVE DECAY DATA                                        403 1451    8
------ENDF-6 FORMAT                                                403 1451    9
****************************************************************** 403 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 403 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 403 1451   12
**             Original data taken from:  NUBASE                ** 403 1451   13
****************************************************************** 403 1451   14
****************************************************************** 403 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 403 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      403 1451   17
                                                                   403 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           403 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        403 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               403 1451   21
****************************************************************** 403 1451   22
                                1        451         24          0 403 1451   23
                                8        457          7          0 403 1451   24
 0.000000+0 0.000000+0          0          0          0          0 403 1  099999
                                                                   403 0  0    0
 2.20390+04 3.86666+01          0          0          0          0 403 8457    1
 3.10000-02 4.00000-03          0          0          6          0 403 8457    2
 3.89696+06 0.00000+00 3.89696+06 0.00000+00 3.89696+06 0.00000+00 403 8457    3
 1.50000+00 1.00000+00          0          0         18          3 403 8457    4
 2.00000+00 0.00000+00 1.56680+07 0.00000+00 2.77556-17 0.00000+00 403 8457    5
 2.70000+00 0.00000+00 1.62700+07 0.00000+00 8.50000-01 0.00000+00 403 8457    6
 2.77000+00 0.00000+00 1.17222+07 0.00000+00 1.50000-01 0.00000+00 403 8457    7
                                                                   403 8  099999
                                                                   403 0  0    0
                                                                     0 0  0    0
 2.204000+4 3.964700+1         -1          0          2          1 404 1451    1
 0.000000+0 1.000000+0          0          0          0          6 404 1451    2
 0.000000+0 0.000000+0          0          0          4        311 404 1451    3
 0.000000+0 0.000000+0          0          0         18          2 404 1451    4
 22-Ti- 40 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  404 1451    5
                      DIST-NOV07                       261107      404 1451    6
----JEFF-311          MATERIAL  404                                404 1451    7
-----RADIOACTIVE DECAY DATA                                        404 1451    8
------ENDF-6 FORMAT                                                404 1451    9
****************************************************************** 404 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 404 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 404 1451   12
**             Original data taken from:  NUBASE                ** 404 1451   13
****************************************************************** 404 1451   14
****************************************************************** 404 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 404 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      404 1451   17
                                                                   404 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           404 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        404 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               404 1451   21
****************************************************************** 404 1451   22
                                1        451         24          0 404 1451   23
                                8        457          5          0 404 1451   24
 0.000000+0 0.000000+0          0          0          0          0 404 1  099999
                                                                   404 0  0    0
 2.20400+04 3.96470+01          0          0          0          0 404 8457    1
 5.33000-02 1.50000-03          0          0          6          0 404 8457    2
 2.78385+06 0.00000+00 2.78385+06 0.00000+00 2.78385+06 0.00000+00 404 8457    3
 0.00000+00 1.00000+00          0          0          6          1 404 8457    4
 2.70000+00 0.00000+00 1.11354+07 0.00000+00 1.00000+00 0.00000+00 404 8457    5
                                                                   404 8  099999
                                                                   404 0  0    0
                                                                     0 0  0    0
 2.204100+4 4.063110+1         -1          0          2          1 405 1451    1
 0.000000+0 1.000000+0          0          0          0          6 405 1451    2
 0.000000+0 0.000000+0          0          0          4        311 405 1451    3
 0.000000+0 0.000000+0          0          0         18          2 405 1451    4
 22-Ti- 41 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  405 1451    5
                      DIST-NOV07                       261107      405 1451    6
----JEFF-311          MATERIAL  405                                405 1451    7
-----RADIOACTIVE DECAY DATA                                        405 1451    8
------ENDF-6 FORMAT                                                405 1451    9
****************************************************************** 405 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 405 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 405 1451   12
**             Original data taken from:  NUBASE                ** 405 1451   13
****************************************************************** 405 1451   14
****************************************************************** 405 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 405 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      405 1451   17
                                                                   405 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           405 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        405 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               405 1451   21
****************************************************************** 405 1451   22
                                1        451         24          0 405 1451   23
                                8        457          5          0 405 1451   24
 0.000000+0 0.000000+0          0          0          0          0 405 1  099999
                                                                   405 0  0    0
 2.20410+04 4.06311+01          0          0          0          0 405 8457    1
 8.09000-02 1.20000-03          0          0          6          0 405 8457    2
 2.96432+06 0.00000+00 2.96432+06 0.00000+00 2.96432+06 0.00000+00 405 8457    3
 1.50000+00 1.00000+00          0          0          6          1 405 8457    4
 2.70000+00 0.00000+00 1.18573+07 0.00000+00 1.00000+00 0.00000+00 405 8457    5
                                                                   405 8  099999
                                                                   405 0  0    0
                                                                     0 0  0    0
 2.204200+4 4.161250+1         -1          0          2          1 406 1451    1
 0.000000+0 1.000000+0          0          0          0          6 406 1451    2
 0.000000+0 0.000000+0          0          0          4        311 406 1451    3
 0.000000+0 0.000000+0          0          0         48          2 406 1451    4
 22-Ti- 42 ENSDF      EVAL-MAR01 CONVERSION OF ENSDF               406 1451    5
 /ENSDF/              DIST-NOV07                       261107      406 1451    6
----JEFF-311          MATERIAL  406                                406 1451    7
-----RADIOACTIVE DECAY DATA                                        406 1451    8
------ENDF-6 FORMAT                                                406 1451    9
****************************************************************** 406 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 406 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 406 1451   12
**             Original data taken from:  ENSDF                 ** 406 1451   13
****************************************************************** 406 1451   14
****************************************************************** 406 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 406 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 406 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 406 1451   18
****************************************************************** 406 1451   19
42TI  DECAY 0.199 S  6                      I(min) = 0.0E+00 %     406 1451   20
         Ex = 0           keV                     1 decay mode(s)  406 1451   21
                                                                   406 1451   22
42TI EC DECAY               Q =  7000.0000 keV       5.0000        406 1451   23
         Branching                100.0000 %         0.0000        406 1451   24
                         Br*Q =  7000.0000 keV       5.0000        406 1451   25
                                              0 isomeric state(s)  406 1451   26
                                                                   406 1451   27
Individual beta+ transitions                                       406 1451   28
Final level    end point    shape    av.energy        intensity    406 1451   29
 1888.000   4089.270   5.063  0   1870.100   2.500    0.700 0.000  406 1451   30
  611.100   5365.941   5.024  0   2492.300   2.500   56.00014.000  406 1451   31
    0.000   5976.932   4.999  0   2792.000   2.500   44.00014.000  406 1451   32
                                                                   406 1451   33
         Mean alpha    energy       0.0000 keV       0.0000        406 1451   34
         Mean beta     energy    2637.2587 keV     523.9627        406 1451   35
         Mean conv. e- energy       0.0000 keV       0.0000        406 1451   36
         Mean Auger e- energy       0.0033 keV       0.0006        406 1451   37
         Mean gamma    energy    1384.5841 keV                     406 1451   38
         Mean X        energy       0.0007 keV       0.0001        406 1451   39
         Mean recoil   energy       1.0140 keV       0.2013        406 1451   40
         Mean neutrino energy    3033.0156 keV     600.5714        406 1451   41
         Mean neutron  energy       0.0000 keV       0.0000        406 1451   42
         Total         energy    7055.8795 keV     826.7322        406 1451   43
         Q effective             7000.0000 keV       5.0000        406 1451   44
         diff. mode                55.8795 keV       0.7983 %      406 1451   45
                                                                   406 1451   46
         Mean e- bind. energy       0.0042 keV                     406 1451   47
         diff. atomic              -0.0002 keV      -4.2321 %      406 1451   48
         diff. nuclear             55.8797 keV       0.7983 %      406 1451   49
                                                                   406 1451   50
         B+ fraction              100.7000 %        19.7990        406 1451   51
                                                                   406 1451   52
                                1        451         54          0 406 1451   53
                                8        457         39          0 406 1451   54
 0.000000+0 0.000000+0          0          0          0          0 406 1  099999
                                                                   406 0  0    0
 2.20420+04 4.16125+01          0          0          0          4 406 8457    1
 1.99000-01 6.00000-03          0          0          6          0 406 8457    2
 2.63726+06 5.23963+05 1.38458+06 2.19689+05 1.01404+03 2.01347+02 406 8457    3
 0.00000+00 1.00000+00          0          0          6          1 406 8457    4
 2.00000+00 0.00000+00 7.00000+06 5.00000+03 1.00000+00 0.00000+00 406 8457    5
 0.00000+00 0.00000+00          0          0          6          2 406 8457    6
 1.00000-02 0.00000+00 3.55432+05 8.55545+04 0.00000+00 0.00000+00 406 8457    7
 6.11100+05 5.00000+02          0          0         12          0 406 8457    8
 2.00000+00 0.00000+00 5.60000+01 1.40000+01 0.00000+00 0.00000+00 406 8457    9
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 406 8457   10
 1.88800+06 8.00000+02          0          0         12          0 406 8457   11
 2.00000+00 0.00000+00 7.00000-01 0.00000+00 0.00000+00 0.00000+00 406 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 406 8457   13
 0.00000+00 2.00000+00          0          0          6          3 406 8457   14
 1.00000-02 0.00000+00 2.63726+06 5.23963+05 0.00000+00 0.00000+00 406 8457   15
 5.11108+06 5.06269+03          0          0          6          0 406 8457   16
 2.00000+00 1.00000+00 7.00000-01 0.00000+00 7.00000-01 0.00000+00 406 8457   17
 6.38776+06 5.02404+03          0          0          6          0 406 8457   18
 2.00000+00 1.00000+00 5.60000+01 1.40000+01 5.60000+01 1.40000+01 406 8457   19
 6.99875+06 4.99910+03          0          0          6          0 406 8457   20
 2.00000+00 1.00000+00 4.40000+01 1.40000+01 4.40000+01 1.40000+01 406 8457   21
 0.00000+00 8.00000+00          0          0          6          2 406 8457   22
 1.00000-02 0.00000+00 3.31841+00 5.52358-01 0.00000+00 0.00000+00 406 8457   23
 3.70000+02 0.00000+00          0          0          6          0 406 8457   24
 2.00000+00 0.00000+00 1.55155-01 2.88495-02 0.00000+00 0.00000+00 406 8457   25
 3.64000+03 0.00000+00          0          0          6          0 406 8457   26
 2.00000+00 0.00000+00 7.53940-02 1.48886-02 0.00000+00 0.00000+00 406 8457   27
 0.00000+00 9.00000+00          0          0          6          5 406 8457   28
 1.00000-02 0.00000+00 1.02915+06 2.47821+05 0.00000+00 0.00000+00 406 8457   29
 4.00000+02 0.00000+00          0          0          6          0 406 8457   30
 2.00000+00 0.00000+00 3.10932-04 1.23230-04 0.00000+00 0.00000+00 406 8457   31
 4.08610+03 2.00000-01          0          0          6          0 406 8457   32
 2.00000+00 0.00000+00 5.23301-03 1.12090-03 0.00000+00 0.00000+00 406 8457   33
 4.09060+03 2.00000-01          0          0          6          0 406 8457   34
 2.00000+00 0.00000+00 1.04036-02 2.22525-03 0.00000+00 0.00000+00 406 8457   35
 4.46000+03 0.00000+00          0          0          6          0 406 8457   36
 2.00000+00 0.00000+00 2.04840-03 4.39850-04 0.00000+00 0.00000+00 406 8457   37
 5.10999+05 1.50000-01          0          0          6          0 406 8457   38
 2.00000+00 0.00000+00 2.01400+02 4.84974+01 0.00000+00 0.00000+00 406 8457   39
                                                                   406 8  099999
                                                                   406 0  0    0
                                                                     0 0  0    0
 2.204300+4 4.259940+1         -1          0          2          1 407 1451    1
 0.000000+0 1.000000+0          0          0          0          6 407 1451    2
 0.000000+0 0.000000+0          0          0          4        311 407 1451    3
 0.000000+0 0.000000+0          0          0         57          2 407 1451    4
 22-Ti- 43 ENSDF      EVAL-MAY01 CONVERSION OF ENSDF               407 1451    5
 /ENSDF/              DIST-NOV07                       261107      407 1451    6
----JEFF-311          MATERIAL  407                                407 1451    7
-----RADIOACTIVE DECAY DATA                                        407 1451    8
------ENDF-6 FORMAT                                                407 1451    9
****************************************************************** 407 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 407 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 407 1451   12
**             Original data taken from:  ENSDF                 ** 407 1451   13
****************************************************************** 407 1451   14
****************************************************************** 407 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 407 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 407 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 407 1451   18
****************************************************************** 407 1451   19
43TI  DECAY 509 MS    5                     I(min) = 0.0E+00 %     407 1451   20
         Ex = 0           keV                     1 decay mode(s)  407 1451   21
                                                                   407 1451   22
43TI EC DECAY               Q =  6867.0000 keV       7.0000        407 1451   23
         Branching                100.0000 %         0.0000        407 1451   24
                         Br*Q =  6867.0000 keV       7.0000        407 1451   25
                                              0 isomeric state(s)  407 1451   26
                                                                   407 1451   27
Individual beta+ transitions                                       407 1451   28
Final level    end point    shape    av.energy        intensity    407 1451   29
 3631.700   2212.922   7.070  0    974.000   4.000    0.016 0.004  407 1451   30
 3259.730   2584.828   7.000  0   1149.000   4.000    0.011 0.002  407 1451   31
 2760.090   3084.383   7.000  0   1386.000   4.000    0.200 0.030  407 1451   32
 2458.680   3385.741   7.000  0   1531.000   4.000    0.910 0.130  407 1451   33
 2335.470   3508.930   7.000  0   1590.000   4.000    0.380 0.060  407 1451   34
 2288.400   3555.992   7.000  0   1613.000   4.000    4.600 0.700  407 1451   35
 1963.000   3881.336   7.010  0   1769.000   4.000    0.022 0.010  407 1451   36
 1882.500   3961.822   7.005  0   1808.000   4.000    0.260 0.050  407 1451   37
 1408.030   4436.211   6.999  0   2039.000   4.000    0.670 0.100  407 1451   38
  845.170   4998.974   6.999  0   2313.000   4.000    2.600 0.400  407 1451   39
  151.250   5692.775   7.000  1   2664.000   4.000    0.035 0.035  407 1451   40
    0.000   5843.999   6.999  0   2727.000   4.000   90.200 1.400  407 1451   41
                                                                   407 1451   42
         Mean alpha    energy       0.0000 keV       0.0000        407 1451   43
         Mean beta     energy    2636.8020 keV      41.1659        407 1451   44
         Mean conv. e- energy       0.0000 keV       0.0000        407 1451   45
         Mean Auger e- energy       0.0036 keV       0.0001        407 1451   46
         Mean gamma    energy    1202.0748 keV                     407 1451   47
         Mean X        energy       0.0008 keV       0.0000        407 1451   48
         Mean recoil   energy       0.9710 keV       0.0152        407 1451   49
         Mean neutrino energy    3029.0397 keV     114.8636        407 1451   50
         Mean neutron  energy       0.0000 keV       0.0000        407 1451   51
         Total         energy    6868.8966 keV     124.0782        407 1451   52
         Q effective             6867.0000 keV       7.0000        407 1451   53
         diff. mode                 1.8966 keV       0.0276 %      407 1451   54
                                                                   407 1451   55
         Mean e- bind. energy       0.0047 keV                     407 1451   56
         diff. atomic              -0.0002 keV      -4.2325 %      407 1451   57
         diff. nuclear              1.8968 keV       0.0276 %      407 1451   58
                                                                   407 1451   59
         B+ fraction               99.9040 %         1.6264        407 1451   60
                                                                   407 1451   61
                                1        451         63          0 407 1451   62
                                8        457        105          0 407 1451   63
 0.000000+0 0.000000+0          0          0          0          0 407 1  099999
                                                                   407 0  0    0
 2.20430+04 4.25994+01          0          0          0          4 407 8457    1
 5.09000-01 5.00000-03          0          0          6          0 407 8457    2
 2.63681+06 4.11659+04 1.20208+06 2.25193+04 0.00000+00 0.00000+00 407 8457    3
 3.50000+00-1.00000+00          0          0          6          1 407 8457    4
 2.00000+00 0.00000+00 6.86700+06 7.00000+03 1.00000+00 0.00000+00 407 8457    5
 0.00000+00 0.00000+00          0          0          6         18 407 8457    6
 1.00000-02 0.00000+00 1.81058+05 1.51930+04 0.00000+00 0.00000+00 407 8457    7
 1.51900+05 0.00000+00          0          0         12          0 407 8457    8
 2.00000+00 0.00000+00 1.27600-01 5.55932-02 0.00000+00 0.00000+00 407 8457    9
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   10
 4.72700+05 4.00000+02          0          0         12          0 407 8457   11
 2.00000+00 0.00000+00 2.11200-01 5.25875-02 0.00000+00 0.00000+00 407 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   13
 5.62900+05 2.00000+02          0          0         12          0 407 8457   14
 2.00000+00 0.00000+00 1.23200-01 2.76810-02 0.00000+00 0.00000+00 407 8457   15
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   16
 8.45200+05 1.00000+02          0          0         12          0 407 8457   17
 2.00000+00 0.00000+00 2.76760+00 3.86548-01 0.00000+00 0.00000+00 407 8457   18
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   19
 8.80700+05 5.00000+02          0          0         12          0 407 8457   20
 2.00000+00 0.00000+00 4.84000-02 1.10000-02 0.00000+00 0.00000+00 407 8457   21
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   22
 9.36000+05 8.00000+02          0          0         12          0 407 8457   23
 2.00000+00 0.00000+00 4.40000-02 1.06508-02 0.00000+00 0.00000+00 407 8457   24
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   25
 1.40800+06 1.00000+02          0          0         12          0 407 8457   26
 2.00000+00 0.00000+00 5.54400-01 7.76216-02 0.00000+00 0.00000+00 407 8457   27
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   28
 1.44350+06 3.00000+02          0          0         12          0 407 8457   29
 2.00000+00 0.00000+00 5.72000-02 1.53323-02 0.00000+00 0.00000+00 407 8457   30
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   31
 1.49020+06 2.00000+02          0          0         12          0 407 8457   32
 2.00000+00 0.00000+00 2.20000-02 9.29731-03 0.00000+00 0.00000+00 407 8457   33
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   34
 1.81540+06 4.00000+02          0          0         12          0 407 8457   35
 2.00000+00 0.00000+00 3.96000-02 2.26530-02 0.00000+00 0.00000+00 407 8457   36
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   37
 1.88250+06 3.00000+02          0          0         12          0 407 8457   38
 2.00000+00 0.00000+00 2.59600-01 4.99219-02 0.00000+00 0.00000+00 407 8457   39
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   40
 2.13710+06 1.00000+02          0          0         12          0 407 8457   41
 2.00000+00 0.00000+00 9.24000-02 2.16453-02 0.00000+00 0.00000+00 407 8457   42
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   43
 2.28830+06 1.00000+02          0          0         12          0 407 8457   44
 2.00000+00 0.00000+00 4.40000+00 6.25281-01 0.00000+00 0.00000+00 407 8457   45
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   46
 2.33540+06 1.00000+02          0          0         12          0 407 8457   47
 2.00000+00 0.00000+00 3.82800-01 6.06092-02 0.00000+00 0.00000+00 407 8457   48
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   49
 2.45860+06 1.00000+02          0          0         12          0 407 8457   50
 2.00000+00 0.00000+00 9.10800-01 1.29092-01 0.00000+00 0.00000+00 407 8457   51
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   52
 2.76000+06 1.00000+02          0          0         12          0 407 8457   53
 2.00000+00 0.00000+00 1.98000-01 3.00540-02 0.00000+00 0.00000+00 407 8457   54
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   55
 3.25960+06 1.00000+03          0          0         12          0 407 8457   56
 2.00000+00 0.00000+00 1.05600-02 2.27403-03 0.00000+00 0.00000+00 407 8457   57
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   58
 3.63150+06 1.00000+03          0          0         12          0 407 8457   59
 2.00000+00 0.00000+00 1.58400-02 3.41104-03 0.00000+00 0.00000+00 407 8457   60
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 407 8457   61
 0.00000+00 2.00000+00          0          0          6         12 407 8457   62
 1.00000-02 0.00000+00 2.63680+06 4.11659+04 0.00000+00 0.00000+00 407 8457   63
 3.23474+06 7.06985+03          0          0          6          0 407 8457   64
 2.00000+00 1.00000+00 1.60000-02 4.00000-03 1.60000-02 4.00000-03 407 8457   65
 3.60665+06 6.99951+03          0          0          6          0 407 8457   66
 2.00000+00 1.00000+00 1.10000-02 2.00000-03 1.10000-02 2.00000-03 407 8457   67
 4.10621+06 6.99951+03          0          0          6          0 407 8457   68
 2.00000+00 1.00000+00 2.00000-01 3.00000-02 2.00000-01 3.00000-02 407 8457   69
 4.40756+06 6.99951+03          0          0          6          0 407 8457   70
 2.00000+00 1.00000+00 9.10000-01 1.30000-01 9.10000-01 1.30000-01 407 8457   71
 4.53075+06 6.99951+03          0          0          6          0 407 8457   72
 2.00000+00 1.00000+00 3.80000-01 6.00000-02 3.80000-01 6.00000-02 407 8457   73
 4.57781+06 6.99951+03          0          0          6          0 407 8457   74
 2.00000+00 1.00000+00 4.60000+00 7.00000-01 4.60000+00 7.00000-01 407 8457   75
 4.90316+06 7.01022+03          0          0          6          0 407 8457   76
 2.00000+00 1.00000+00 2.20000-02 1.00000-02 2.20000-02 1.00000-02 407 8457   77
 4.98364+06 7.00522+03          0          0          6          0 407 8457   78
 2.00000+00 1.00000+00 2.60000-01 5.00000-02 2.60000-01 5.00000-02 407 8457   79
 5.45803+06 6.99938+03          0          0          6          0 407 8457   80
 2.00000+00 1.00000+00 6.70000-01 1.00000-01 6.70000-01 1.00000-01 407 8457   81
 6.02080+06 6.99938+03          0          0          6          0 407 8457   82
 2.00000+00 1.00000+00 2.60000+00 4.00000-01 2.60000+00 4.00000-01 407 8457   83
 6.71460+06 7.00020+03          0          0          6          0 407 8457   84
 2.00000+00 2.00000+00 3.50000-02 3.50000-02 3.50000-02 3.50000-02 407 8457   85
 6.86582+06 6.99880+03          0          0          6          0 407 8457   86
 2.00000+00 1.00000+00 9.03000+01 1.40000+00 9.02000+01 1.40000+00 407 8457   87
 0.00000+00 8.00000+00          0          0          6          2 407 8457   88
 1.00000-02 0.00000+00 3.64937+00 1.04691-01 0.00000+00 0.00000+00 407 8457   89
 3.70000+02 0.00000+00          0          0          6          0 407 8457   90
 2.00000+00 0.00000+00 1.70643-01 5.41042-03 0.00000+00 0.00000+00 407 8457   91
 3.64000+03 0.00000+00          0          0          6          0 407 8457   92
 2.00000+00 0.00000+00 8.29118-02 2.82306-03 0.00000+00 0.00000+00 407 8457   93
 0.00000+00 9.00000+00          0          0          6          5 407 8457   94
 1.00000-02 0.00000+00 1.02102+06 4.95643+04 0.00000+00 0.00000+00 407 8457   95
 4.00000+02 0.00000+00          0          0          6          0 407 8457   96
 2.00000+00 0.00000+00 3.41970-04 1.20179-04 0.00000+00 0.00000+00 407 8457   97
 4.08610+03 2.00000-01          0          0          6          0 407 8457   98
 2.00000+00 0.00000+00 5.75482-03 5.16094-04 0.00000+00 0.00000+00 407 8457   99
 4.09060+03 2.00000-01          0          0          6          0 407 8457  100
 2.00000+00 0.00000+00 1.14410-02 1.01766-03 0.00000+00 0.00000+00 407 8457  101
 4.46000+03 0.00000+00          0          0          6          0 407 8457  102
 2.00000+00 0.00000+00 2.25265-03 2.04862-04 0.00000+00 0.00000+00 407 8457  103
 5.10999+05 1.50000-01          0          0          6          0 407 8457  104
 2.00000+00 0.00000+00 1.99808+02 9.69948+00 0.00000+00 0.00000+00 407 8457  105
                                                                   407 8  099999
                                                                   407 0  0    0
                                                                     0 0  0    0
 2.204400+4 4.358210+1         -1          0          2          1 408 1451    1
 0.000000+0 1.000000+0          0          0          0          6 408 1451    2
 0.000000+0 0.000000+0          0          0          4        311 408 1451    3
 0.000000+0 0.000000+0          0          0         48          2 408 1451    4
 22-Ti- 44 BRK        EVAL-OCT01 E.BROWNE                          408 1451    5
 /DDEP/               DIST-NOV07                       261107      408 1451    6
----JEFF-311          MATERIAL  408                                408 1451    7
-----RADIOACTIVE DECAY DATA                                        408 1451    8
------ENDF-6 FORMAT                                                408 1451    9
****************************************************************** 408 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 408 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 408 1451   12
**             Original data taken from:  LNHB                  ** 408 1451   13
****************************************************************** 408 1451   14
****************************************************************** 408 1451   15
*Data from the Laboratoire National Henri Becquerel, BNM-CEA/LNHB* 408 1451   16
*              http://www.nucleide.org/NucData.htm               * 408 1451   17
****************************************************************** 408 1451   18
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 408 1451   19
*     (the CEA-Bruyeres version of the RADLST program).          * 408 1451   20
* (1) 0. Bersillon and J. Blachot, to be published.              * 408 1451   21
****************************************************************** 408 1451   22
DECAY 60.0 Y    11                    I(min) = 0.0E+00 %           408 1451   23
         Ex = 0.0         keV                     1 decay mode(s)  408 1451   24
                                                                   408 1451   25
 44TI EC DECAY              Q =   267.5000 keV       1.9000        408 1451   26
         Branching                100.0000 %         0.0000        408 1451   27
                         Br*Q =   267.5000 keV       1.9000        408 1451   28
                                              0 isomeric state(s)  408 1451   29
                                                                   408 1451   30
Individual beta+ transitions                                       408 1451   31
Final level    end point    shape    av.energy        intensity    408 1451   32
                                                                   408 1451   33
         Mean alpha    energy       0.0000 keV       0.0000        408 1451   34
         Mean beta     energy       0.0000 keV       0.0000        408 1451   35
         Mean conv. e- energy       7.1104 keV       0.1521        408 1451   36
         Mean Auger e- energy       3.5166 keV       0.0596        408 1451   37
         Mean gamma    energy     137.4868 keV                     408 1451   38
         Mean X        energy       0.7753 keV       0.0436        408 1451   39
         Mean recoil   energy       0.0000 keV       0.0000        408 1451   40
         Mean neutrino energy     118.4117 keV       1.9294        408 1451   41
         Mean neutron  energy       0.0000 keV       0.0000        408 1451   42
         Total         energy     267.3009 keV       2.4476        408 1451   43
         Q effective              267.5000 keV       1.9000        408 1451   44
         diff. mode                -0.1991 keV      -0.0744 %      408 1451   45
                                                                   408 1451   46
         Mean e- bind. energy       4.4822 keV                     408 1451   47
         diff. atomic              -0.1903 keV      -4.2453 %      408 1451   48
         diff. nuclear             -0.0088 keV      -0.0033 %      408 1451   49
                                                                   408 1451   50
         B+ fraction                0.0000 %         0.0000        408 1451   51
                                                                   408 1451   52
                                1        451         54          0 408 1451   53
                                8        457         56          0 408 1451   54
 0.000000+0 0.000000+0          0          0          0          0 408 1  099999
                                                                   408 0  0    0
 2.20440+04 4.35821+01          0          0          0          4 408 8457    1
 1.89342+09 3.47126+07          0          0          6          0 408 8457    2
 1.06270+04 1.63342+02 1.38262+05 1.49722+03 0.00000+00 0.00000+00 408 8457    3
 0.00000+00 1.00000+00          0          0          6          1 408 8457    4
 2.00000+00 0.00000+00 2.67500+05 1.90000+03 1.00000+00 0.00000+00 408 8457    5
 0.00000+00 0.00000+00          0          0          6          3 408 8457    6
 1.00000-02 0.00000+00 1.37487+05 1.49659+03 0.00000+00 0.00000+00 408 8457    7
 6.78679+04 1.40000+00          0          0         12          0 408 8457    8
 2.00000+00 0.00000+00 9.21200+01 2.20000-01 0.00000+00 0.00000+00 408 8457    9
 8.45000-02 0.00000+00 7.66000-02 2.29800-03 6.65000-03 1.99500-04 408 8457   10
 7.83600+04 3.00000+01          0          0         12          0 408 8457   11
 2.00000+00 0.00000+00 9.55000+01 1.90000+00 0.00000+00 0.00000+00 408 8457   12
 3.02000-02 0.00000+00 2.73000-02 8.19000-04 2.44000-03 7.32000-05 408 8457   13
 1.46220+05 3.00000+01          0          0         12          0 408 8457   14
 2.00000+00 0.00000+00 9.10000-02 3.00000-03 0.00000+00 0.00000+00 408 8457   15
 4.60000-02 0.00000+00 4.14000-02 1.24200-03 3.85000-03 1.15500-04 408 8457   16
 0.00000+00 2.00000+00          0          0          6          2 408 8457   17
 1.00000-02 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 408 8457   18
 1.21280+05 1.90024+03          0          0          6          0 408 8457   19
 2.00000+00 1.00000+00 9.85000+01 2.00000-01 0.00000+00 0.00000+00 408 8457   20
 1.99632+05 1.90000+03          0          0          6          0 408 8457   21
 2.00000+00 1.00000+00 1.50000+00 2.00000-01 0.00000+00 0.00000+00 408 8457   22
 0.00000+00 8.00000+00          0          0          6         11 408 8457   23
 1.00000-02 0.00000+00 1.06270+04 1.63342+02 0.00000+00 0.00000+00 408 8457   24
 3.70000+02 0.00000+00          0          0          6          0 408 8457   25
 2.00000+00 0.00000+00 1.64885+02 3.02226+00 0.00000+00 0.00000+00 408 8457   26
 3.64000+03 0.00000+00          0          0          6          0 408 8457   27
 2.00000+00 0.00000+00 7.98508+01 1.60945+00 0.00000+00 0.00000+00 408 8457   28
 6.33751+04 1.45602+00          0          0          6          0 408 8457   29
 2.00000+00 0.00000+00 7.05639+00 2.12361-01 0.00000+00 0.00000+00 408 8457   30
 6.73675+04 1.45602+00          0          0          6          0 408 8457   31
 2.00000+00 0.00000+00 6.12598-01 1.84361-02 0.00000+00 0.00000+00 408 8457   32
 6.78141+04 1.45602+00          0          0          6          0 408 8457   33
 2.00000+00 0.00000+00 1.15150-01 3.46543-03 0.00000+00 0.00000+00 408 8457   34
 7.38672+04 3.00027+01          0          0          6          0 408 8457   35
 2.00000+00 0.00000+00 2.60715+00 9.38510-02 0.00000+00 0.00000+00 408 8457   36
 7.78596+04 3.00027+01          0          0          6          0 408 8457   37
 2.00000+00 0.00000+00 2.33020-01 8.38815-03 0.00000+00 0.00000+00 408 8457   38
 7.83062+04 3.00027+01          0          0          6          0 408 8457   39
 2.00000+00 0.00000+00 4.39300-02 1.58137-03 0.00000+00 0.00000+00 408 8457   40
 1.41727+05 3.00027+01          0          0          6          0 408 8457   41
 2.00000+00 0.00000+00 3.76740-03 1.67927-04 0.00000+00 0.00000+00 408 8457   42
 1.45720+05 3.00027+01          0          0          6          0 408 8457   43
 2.00000+00 0.00000+00 3.50350-04 1.56164-05 0.00000+00 0.00000+00 408 8457   44
 1.46166+05 3.00027+01          0          0          6          0 408 8457   45
 2.00000+00 0.00000+00 6.82500-05 3.04216-06 0.00000+00 0.00000+00 408 8457   46
 0.00000+00 9.00000+00          0          0          6          4 408 8457   47
 1.00000-02 0.00000+00 7.75273+02 4.35751+01 0.00000+00 0.00000+00 408 8457   48
 4.00000+02 0.00000+00          0          0          6          0 408 8457   49
 2.00000+00 0.00000+00 3.30430-01 1.15809-01 0.00000+00 0.00000+00 408 8457   50
 4.08610+03 2.00000-01          0          0          6          0 408 8457   51
 2.00000+00 0.00000+00 5.54235+00 4.73197-01 0.00000+00 0.00000+00 408 8457   52
 4.09060+03 2.00000-01          0          0          6          0 408 8457   53
 2.00000+00 0.00000+00 1.10186+01 9.32279-01 0.00000+00 0.00000+00 408 8457   54
 4.46000+03 0.00000+00          0          0          6          0 408 8457   55
 2.00000+00 0.00000+00 2.16948+00 1.88102-01 0.00000+00 0.00000+00 408 8457   56
                                                                   408 8  099999
                                                                   408 0  0    0
                                                                     0 0  0    0
 2.204500+4 4.457190+1         -1          0          2          1 409 1451    1
 0.000000+0 1.000000+0          0          0          0          6 409 1451    2
 0.000000+0 0.000000+0          0          0          4        311 409 1451    3
 0.000000+0 0.000000+0          0          0         46          2 409 1451    4
 22-Ti- 45 HAR+WIN    EVAL-APR92 A.L. NICHOLS                      409 1451    5
                      DIST-NOV07                       261107      409 1451    6
----JEFF-311          MATERIAL  409                                409 1451    7
-----RADIOACTIVE DECAY DATA                                        409 1451    8
------ENDF-6 FORMAT                                                409 1451    9
****************************************************************** 409 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 409 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 409 1451   12
**             Original data taken from:  UKPADD67              ** 409 1451   13
****************************************************************** 409 1451   14
      T.W.BURROWS             NUCL DATA SHEETS 65(1992)1           409 1451   15
      T.W.BURROWS             NUCL DATA SHEETS 40(1983)149         409 1451   16
      F.T.PORTER ET AL        PHYS REV 146(1966)774                409 1451   17
      W.M.ZUK ET AL           Z PHYSIK 242(1971)93                 409 1451   18
      G.P.BOROZENETS          J NUCL PHYS USSR 43(1986)14          409 1451   19
                                                                   409 1451   20
          THE DECAY SCHEME WAS DERIVED FROM THE ABSOLUTE           409 1451   21
      GAMMA-RAY EMISSION PROBABILITY MEASUREMENTS OF ZUK ET        409 1451   22
      AL COMBINED WITH THE HIGH-ENERGY GAMMA-RAY STUDIES OF        409 1451   23
      BOROZENETS. THESE DATA WERE USED TO CALCULATE THE EC         409 1451   24
      TRANSITION TO THE GROUND STATE OF SC-45 AS 0.9969(3).        409 1451   25
          POSITRON EMISSION PROBABILITIES WERE CALCULATED ON       409 1451   26
      A THEORETICAL BASIS. FURTHER MEASUREMENTS ARE STRONGLY       409 1451   27
      RECOMMENDED TO CONFIRM THE VALIDITY OF THE PROPOSED          409 1451   28
      DECAY SCHEME WHICH IS HIGHLY DEPENDENT ON THE SINGLE         409 1451   29
      SET OF DATA REPORTED BY ZUK ET AL.                           409 1451   30
                                                                   409 1451   31
                                                                   409 1451   32
      MEAN BETA+ ENERGIES:-                                        409 1451   33
   END POINT(MEV)= 0.3205  SHAPE= 0  MEAN= 0.1338  INT= 0.0001     409 1451   34
   END POINT(MEV)= 1.0406  SHAPE= 0  MEAN= 0.4397  INT= 0.8490     409 1451   35
                                                                   409 1451   36
      MEAN GAMMA ENERGY              =      3.3670  KEV            409 1451   37
      MAX. ANNIHILATION INTENSITY    =      1.6983                 409 1451   38
      MEAN BETA+ ENERGY              =    372.8346  KEV            409 1451   39
      BETA+ + NEUTRINO ENERGY        =   2059.1877  KEV            409 1451   40
      MEAN X-RAY ENERGY              =      0.1062  KEV            409 1451   41
      MEAN AUGER ELECTRON ENERGY     =      0.5076  KEV            409 1451   42
      MEAN CONVERSION ELECTRON ENERGY=      0.0008  KEV            409 1451   43
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.5504  KEV            409 1451   44
      EFFECTIVE Q VALUE              =   2062.6001  KEV            409 1451   45
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.1164                 409 1451   46
      CALCULATED Q VALUE             =   2062.5549  KEV            409 1451   47
      % DEVIATION                    =      0.0022                 409 1451   48
                                                                   409 1451   49
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).          409 1451   50
                                1        451         52          1 409 1451   51
                                8        457         90          1 409 1451   52
 0.000000+0 0.000000+0          0          0          0          0 409 1  099999
                                                                   409 0  0    0
2.20450E+044.45719E+01          0          0          0          4 409 8457    1
1.10880E+043.60000E+01          0          0          6          0 409 8457    2
3.73343E+054.53540E+028.71845E+053.17692E+020.00000E+000.00000E+00 409 8457    3
3.50000E+00-1.0000E+00          0          0          6          1 409 8457    4
2.00000E+000.00000E+002.06260E+062.40000E+031.00000E+000.00000E+00 409 8457    5
0.00000E+000.00000E+00          0          0          6         15 409 8457    6
1.54000E-031.54000E-073.36699E+031.71716E+020.00000E+000.00000E+00 409 8457    7
1.23960E+042.00000E+01          0          0         12          0 409 8457    8
2.00000E+000.00000E+001.62338E-043.24675E-050.00000E+000.00000E+00 409 8457    9
3.95000E+022.80450E+013.30000E+022.34300E+015.50000E+013.90500E+00 409 8457   10
3.64100E+052.00000E+02          0          0         12          0 409 8457   11
2.00000E+000.00000E+003.70130E-028.44156E-030.00000E+000.00000E+00 409 8457   12
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   13
4.25300E+057.00000E+02          0          0         12          0 409 8457   14
2.00000E+000.00000E+008.89610E-021.29870E-020.00000E+000.00000E+00 409 8457   15
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   16
4.31300E+053.00000E+02          0          0         12          0 409 8457   17
2.00000E+000.00000E+009.09091E-035.19481E-030.00000E+000.00000E+00 409 8457   18
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   19
5.30700E+052.00000E+02          0          0         12          0 409 8457   20
2.00000E+000.00000E+007.14286E-032.59740E-030.00000E+000.00000E+00 409 8457   21
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   22
5.43100E+051.00000E+02          0          0         12          0 409 8457   23
2.00000E+000.00000E+005.84416E-032.59740E-030.00000E+000.00000E+00 409 8457   24
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   25
7.20100E+051.00000E+02          0          0         12          0 409 8457   26
2.00000E+000.00000E+001.00000E+007.79221E-020.00000E+000.00000E+00 409 8457   27
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   28
9.62000E+053.00000E+02          0          0         12          0 409 8457   29
2.00000E+000.00000E+001.94805E-022.59740E-030.00000E+000.00000E+00 409 8457   30
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   31
9.74400E+052.00000E+02          0          0         12          0 409 8457   32
2.00000E+000.00000E+003.76623E-024.54545E-030.00000E+000.00000E+00 409 8457   33
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   34
1.03240E+063.00000E+02          0          0         12          0 409 8457   35
2.00000E+000.00000E+003.11688E-023.89610E-030.00000E+000.00000E+00 409 8457   36
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   37
1.23670E+063.00000E+02          0          0         12          0 409 8457   38
2.00000E+000.00000E+007.66234E-028.44156E-030.00000E+000.00000E+00 409 8457   39
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   40
1.40890E+062.00000E+02          0          0         12          0 409 8457   41
2.00000E+000.00000E+005.54545E-015.90909E-020.00000E+000.00000E+00 409 8457   42
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   43
1.66200E+064.00000E+02          0          0         12          0 409 8457   44
2.00000E+000.00000E+002.64286E-012.79221E-020.00000E+000.00000E+00 409 8457   45
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   46
1.78760E+065.00000E+02          0          0         12          0 409 8457   47
2.00000E+000.00000E+003.70130E-045.19481E-050.00000E+000.00000E+00 409 8457   48
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   49
1.80000E+065.00000E+02          0          0         12          0 409 8457   50
2.00000E+000.00000E+002.66234E-045.19481E-050.00000E+000.00000E+00 409 8457   51
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 409 8457   52
0.00000E+002.00000E+00          0          0          6          6 409 8457   53
1.00000E+001.00000E-043.72835E+054.50690E+020.00000E+000.00000E+00 409 8457   54
2.63000E+053.00000E+03          0          0          6          0 409 8457   55
2.00000E+001.00000E+009.80000E-071.60000E-070.00000E+000.00000E+00 409 8457   56
4.01000E+053.00000E+03          0          0          6          0 409 8457   57
2.00000E+001.00000E+005.40000E-046.00000E-050.00000E+000.00000E+00 409 8457   58
6.54000E+053.00000E+03          0          0          6          0 409 8457   59
2.00000E+001.00000E+009.00000E-041.00000E-040.00000E+000.00000E+00 409 8457   60
1.08800E+063.00000E+03          0          0          6          0 409 8457   61
2.00000E+001.00000E+001.00000E-042.00000E-050.00000E+000.00000E+00 409 8457   62
1.34250E+062.50000E+03          0          0          6          0 409 8457   63
2.00000E+001.00000E+001.54000E-031.20000E-041.40000E-041.09091E-05 409 8457   64
2.06260E+062.40000E+03          0          0          6          0 409 8457   65
2.00000E+001.00000E+009.96900E-013.00000E-048.49000E-012.55492E-04 409 8457   66
0.00000E+008.00000E+00          0          0          6          6 409 8457   67
1.00000E+000.00000E+005.08447E+025.08447E+010.00000E+000.00000E+00 409 8457   68
2.63000E+011.31500E+00          0          0          6          0 409 8457   69
2.00000E+000.00000E+004.97588E-014.97588E-020.00000E+000.00000E+00 409 8457   70
3.50000E+021.75000E+01          0          0          6          0 409 8457   71
2.00000E+000.00000E+002.39261E-012.39261E-020.00000E+000.00000E+00 409 8457   72
3.74900E+031.87450E+02          0          0          6          0 409 8457   73
2.00000E+000.00000E+001.09568E-011.09568E-020.00000E+000.00000E+00 409 8457   74
7.90320E+033.95160E+02          0          0          6          0 409 8457   75
2.00000E+000.00000E+008.25000E-058.25000E-060.00000E+000.00000E+00 409 8457   76
1.19938E+045.99690E+02          0          0          6          0 409 8457   77
2.00000E+000.00000E+001.37500E-051.37500E-060.00000E+000.00000E+00 409 8457   78
1.23697E+046.18485E+02          0          0          6          0 409 8457   79
2.00000E+000.00000E+002.50000E-062.50000E-070.00000E+000.00000E+00 409 8457   80
0.00000E+009.00000E+00          0          0          6          4 409 8457   81
1.00000E+000.00000E+008.67927E+058.67927E+040.00000E+000.00000E+00 409 8457   82
4.08610E+038.17220E+01          0          0          6          0 409 8457   83
2.00000E+000.00000E+007.60452E-037.60452E-040.00000E+000.00000E+00 409 8457   84
4.09060E+038.18120E+01          0          0          6          0 409 8457   85
2.00000E+000.00000E+001.51183E-021.51183E-030.00000E+000.00000E+00 409 8457   86
4.46000E+038.92000E+01          0          0          6          0 409 8457   87
2.00000E+000.00000E+002.97831E-032.97831E-040.00000E+000.00000E+00 409 8457   88
5.11000E+050.00000E+00          0          0          6          0 409 8457   89
2.00000E+000.00000E+001.69828E+001.69828E-010.00000E+000.00000E+00 409 8457   90
                                                                   409 8  099999
                                                                   409 0  0    0
                                                                     0 0  0    0
 2.204600+4 4.555790+1         -1          0          2          1 410 1451    1
 0.000000+0 0.000000+0          0          0          0          6 410 1451    2
 0.000000+0 0.000000+0          0          0          4        311 410 1451    3
 0.000000+0 0.000000+0          0          0         22          2 410 1451    4
 22-Ti- 46 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  410 1451    5
                      DIST-NOV07                       261107      410 1451    6
----JEFF-311          MATERIAL  410                                410 1451    7
-----RADIOACTIVE DECAY DATA                                        410 1451    8
------ENDF-6 FORMAT                                                410 1451    9
****************************************************************** 410 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 410 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 410 1451   12
**             Original data taken from:  NUBASE                ** 410 1451   13
****************************************************************** 410 1451   14
****************************************************************** 410 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 410 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      410 1451   17
                                                                   410 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           410 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        410 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               410 1451   21
****************************************************************** 410 1451   22
STABLE NUCLEUS                                                     410 1451   23
       SPIN          0.0                                           410 1451   24
       PARITY        1.0                                           410 1451   25
NATURAL ABUNDANCE    8.25 3      %                                 410 1451   26
                                1        451         28          0 410 1451   27
                                8        457          5          0 410 1451   28
 0.000000+0 0.000000+0          0          0          0          0 410 1  099999
                                                                   410 0  0    0
 2.20460+04 4.55579+01          0          0          1          0 410 8457    1
 0.00000+00 0.00000+00          0          0          6          0 410 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 410 8457    3
 0.00000+00 1.00000+00          0          0          6          0 410 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 410 8457    5
                                                                   410 8  099999
                                                                   410 0  0    0
                                                                     0 0  0    0
 2.204700+4 4.654840+1         -1          0          2          1 411 1451    1
 0.000000+0 0.000000+0          0          0          0          6 411 1451    2
 0.000000+0 0.000000+0          0          0          4        311 411 1451    3
 0.000000+0 0.000000+0          0          0         22          2 411 1451    4
 22-Ti- 47 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  411 1451    5
                      DIST-NOV07                       261107      411 1451    6
----JEFF-311          MATERIAL  411                                411 1451    7
-----RADIOACTIVE DECAY DATA                                        411 1451    8
------ENDF-6 FORMAT                                                411 1451    9
****************************************************************** 411 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 411 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 411 1451   12
**             Original data taken from:  NUBASE                ** 411 1451   13
****************************************************************** 411 1451   14
****************************************************************** 411 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 411 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      411 1451   17
                                                                   411 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           411 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        411 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               411 1451   21
****************************************************************** 411 1451   22
STABLE NUCLEUS                                                     411 1451   23
       SPIN          2.5                                           411 1451   24
       PARITY       -1.0                                           411 1451   25
NATURAL ABUNDANCE    7.44 2      %                                 411 1451   26
                                1        451         28          0 411 1451   27
                                8        457          5          0 411 1451   28
 0.000000+0 0.000000+0          0          0          0          0 411 1  099999
                                                                   411 0  0    0
 2.20470+04 4.65484+01          0          0          1          0 411 8457    1
 0.00000+00 0.00000+00          0          0          6          0 411 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 411 8457    3
 2.50000+00-1.00000+00          0          0          6          0 411 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 411 8457    5
                                                                   411 8  099999
                                                                   411 0  0    0
                                                                     0 0  0    0
 2.204800+4 4.753610+1         -1          0          2          1 412 1451    1
 0.000000+0 0.000000+0          0          0          0          6 412 1451    2
 0.000000+0 0.000000+0          0          0          4        311 412 1451    3
 0.000000+0 0.000000+0          0          0         22          2 412 1451    4
 22-Ti- 48 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  412 1451    5
                      DIST-NOV07                       261107      412 1451    6
----JEFF-311          MATERIAL  412                                412 1451    7
-----RADIOACTIVE DECAY DATA                                        412 1451    8
------ENDF-6 FORMAT                                                412 1451    9
****************************************************************** 412 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 412 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 412 1451   12
**             Original data taken from:  NUBASE                ** 412 1451   13
****************************************************************** 412 1451   14
****************************************************************** 412 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 412 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      412 1451   17
                                                                   412 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           412 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        412 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               412 1451   21
****************************************************************** 412 1451   22
STABLE NUCLEUS                                                     412 1451   23
       SPIN          0.0                                           412 1451   24
       PARITY        1.0                                           412 1451   25
NATURAL ABUNDANCE   73.72 3      %                                 412 1451   26
                                1        451         28          0 412 1451   27
                                8        457          5          0 412 1451   28
 0.000000+0 0.000000+0          0          0          0          0 412 1  099999
                                                                   412 0  0    0
 2.20480+04 4.75361+01          0          0          1          0 412 8457    1
 0.00000+00 0.00000+00          0          0          6          0 412 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 412 8457    3
 0.00000+00 1.00000+00          0          0          6          0 412 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 412 8457    5
                                                                   412 8  099999
                                                                   412 0  0    0
                                                                     0 0  0    0
 2.204900+4 4.852740+1         -1          0          2          1 413 1451    1
 0.000000+0 0.000000+0          0          0          0          6 413 1451    2
 0.000000+0 0.000000+0          0          0          4        311 413 1451    3
 0.000000+0 0.000000+0          0          0         22          2 413 1451    4
 22-Ti- 49 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  413 1451    5
                      DIST-NOV07                       261107      413 1451    6
----JEFF-311          MATERIAL  413                                413 1451    7
-----RADIOACTIVE DECAY DATA                                        413 1451    8
------ENDF-6 FORMAT                                                413 1451    9
****************************************************************** 413 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 413 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 413 1451   12
**             Original data taken from:  NUBASE                ** 413 1451   13
****************************************************************** 413 1451   14
****************************************************************** 413 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 413 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      413 1451   17
                                                                   413 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           413 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        413 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               413 1451   21
****************************************************************** 413 1451   22
STABLE NUCLEUS                                                     413 1451   23
       SPIN          3.5                                           413 1451   24
       PARITY       -1.0                                           413 1451   25
NATURAL ABUNDANCE    5.41 2      %                                 413 1451   26
                                1        451         28          0 413 1451   27
                                8        457          5          0 413 1451   28
 0.000000+0 0.000000+0          0          0          0          0 413 1  099999
                                                                   413 0  0    0
 2.20490+04 4.85274+01          0          0          1          0 413 8457    1
 0.00000+00 0.00000+00          0          0          6          0 413 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 413 8457    3
 3.50000+00-1.00000+00          0          0          6          0 413 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 413 8457    5
                                                                   413 8  099999
                                                                   413 0  0    0
                                                                     0 0  0    0
 2.205000+4 4.951570+1         -1          0          2          1 414 1451    1
 0.000000+0 0.000000+0          0          0          0          6 414 1451    2
 0.000000+0 0.000000+0          0          0          4        311 414 1451    3
 0.000000+0 0.000000+0          0          0         22          2 414 1451    4
 22-Ti- 50 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  414 1451    5
                      DIST-NOV07                       261107      414 1451    6
----JEFF-311          MATERIAL  414                                414 1451    7
-----RADIOACTIVE DECAY DATA                                        414 1451    8
------ENDF-6 FORMAT                                                414 1451    9
****************************************************************** 414 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 414 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 414 1451   12
**             Original data taken from:  NUBASE                ** 414 1451   13
****************************************************************** 414 1451   14
****************************************************************** 414 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 414 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      414 1451   17
                                                                   414 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           414 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        414 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               414 1451   21
****************************************************************** 414 1451   22
STABLE NUCLEUS                                                     414 1451   23
       SPIN          0.0                                           414 1451   24
       PARITY        1.0                                           414 1451   25
NATURAL ABUNDANCE    5.18 2      %                                 414 1451   26
                                1        451         28          0 414 1451   27
                                8        457          5          0 414 1451   28
 0.000000+0 0.000000+0          0          0          0          0 414 1  099999
                                                                   414 0  0    0
 2.20500+04 4.95157+01          0          0          1          0 414 8457    1
 0.00000+00 0.00000+00          0          0          6          0 414 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 414 8457    3
 0.00000+00 1.00000+00          0          0          6          0 414 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 414 8457    5
                                                                   414 8  099999
                                                                   414 0  0    0
                                                                     0 0  0    0
 2.205100+4 5.050900+1         -1          0          2          1 415 1451    1
 0.000000+0 1.000000+0          0          0          0          6 415 1451    2
 0.000000+0 0.000000+0          0          0          4        311 415 1451    3
 0.000000+0 0.000000+0          0          0         46          2 415 1451    4
 22-Ti- 51 HAR+WIN    EVAL-JAN92 A.L. NICHOLS                      415 1451    5
                      DIST-NOV07                       261107      415 1451    6
----JEFF-311          MATERIAL  415                                415 1451    7
-----RADIOACTIVE DECAY DATA                                        415 1451    8
------ENDF-6 FORMAT                                                415 1451    9
****************************************************************** 415 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 415 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 415 1451   12
**             Original data taken from:  UKPADD67              ** 415 1451   13
****************************************************************** 415 1451   14
      ZHOU CHUNMEI ET AL      NUCL DATA SHEETS 48(1986)111         415 1451   15
      B.W.SARGENT ET AL       CAN J PHYS 31(1953)235               415 1451   16
      M.E.BUNKER, J.W.STARNER        PHYS REV 97(1955)1272         415 1451   17
      M.E.BUNKER, J.W.STARNER        PHYS REV 99(1955)1906,        415 1451   18
                                                   ERRATUM         415 1451   19
      T.HAYASHI ET AL         J PHYS SOC JAPAN 27(1969)1375        415 1451   20
      V.D.AVCHUKHOV ET AL     BULL ACAD SCI USSR, PHYS SER         415 1451   21
                                               35(1972)772         415 1451   22
                                                                   415 1451   23
          THE GAMMA-RAY MEASUREMENTS OF BUNKER AND STARNER,        415 1451   24
      HAYASHI ET AL, AND AVCHUKHOV ET AL WERE USED TO DERIVE A     415 1451   25
      SIMPLE DECAY SCHEME. THE UNCERTAINTIES OF THE GAMMA-RAY      415 1451   26
      EMISSION PROBABILITIES ARE ILL-DEFINED, AND FURTHER STUDIES  415 1451   27
      ARE REQUIRED TO DETERMINE THEIR ABSOLUTE VALUES. BUNKER AND  415 1451   28
      STARNER (ERRATUM) CALCULATED A K-INTERNAL CONVERSION         415 1451   29
      COEFFICIENT OF 0.00147 FOR THE 320.1KEV GAMMA-RAY            415 1451   30
      TRANSITION, WHICH WAS ADOPTED IN THIS EVALUATION.            415 1451   31
                                                                   415 1451   32
                                                                   415 1451   33
      MEAN BETA- ENERGIES:-                                        415 1451   34
   END POINT(MEV)= 1.5439  SHAPE= 0  MEAN= 0.6093  INT= 0.0700     415 1451   35
   END POINT(MEV)= 2.1525  SHAPE= 0  MEAN= 0.8907  INT= 0.9300     415 1451   36
                                                                   415 1451   37
      MEAN GAMMA ENERGY              =    362.0338  KEV            415 1451   38
      MEAN BETA- ENERGY              =    868.4458  KEV            415 1451   39
      BETA- + NEUTRINO ENERGY        =   2109.8979  KEV            415 1451   40
      MEAN X-RAY ENERGY              =      0.0017  KEV            415 1451   41
      MEAN AUGER ELECTRON ENERGY     =      0.0059  KEV            415 1451   42
      MEAN CONVERSION ELECTRON ENERGY=      0.4808  KEV            415 1451   43
      INTERNAL BREMSSTRAHLUNG ENERGY =      2.5200  KEV            415 1451   44
      EFFECTIVE Q VALUE              =   2472.6001  KEV            415 1451   45
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0688                 415 1451   46
      CALCULATED Q VALUE             =   2472.4199  KEV            415 1451   47
      % DEVIATION                    =      0.0073                 415 1451   48
                                                                   415 1451   49
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).          415 1451   50
                                1        451         52          1 415 1451   51
                                8        457         44          1 415 1451   52
 0.000000+0 0.000000+0          0          0          0          0 415 1  099999
                                                                   415 0  0    0
2.20510E+045.05090E+01          0          0          0          4 415 8457    1
3.48000E+021.80000E+00          0          0          6          0 415 8457    2
8.68932E+051.20462E+043.64555E+059.47994E+030.00000E+000.00000E+00 415 8457    3
1.50000E+00-1.0000E+00          0          0          6          1 415 8457    4
1.00000E+000.00000E+002.47260E+061.70000E+031.00000E+000.00000E+00 415 8457    5
0.00000E+000.00000E+00          0          0          6          3 415 8457    6
9.42000E-019.00000E-033.62034E+059.47659E+030.00000E+000.00000E+00 415 8457    7
3.20085E+051.00000E+00          0          0         12          0 415 8457    8
1.00000E+000.00000E+001.00000E+000.00000E+000.00000E+000.00000E+00 415 8457    9
1.62000E-031.00440E-041.47000E-039.11400E-051.40000E-048.68000E-06 415 8457   10
6.08570E+057.00000E+01          0          0         12          0 415 8457   11
1.00000E+000.00000E+001.40000E-022.00000E-030.00000E+000.00000E+00 415 8457   12
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 415 8457   13
9.28660E+057.00000E+01          0          0         12          0 415 8457   14
1.00000E+000.00000E+006.00000E-021.00000E-020.00000E+000.00000E+00 415 8457   15
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 415 8457   16
0.00000E+001.00000E+00          0          0          6          2 415 8457   17
1.00000E+000.00000E+008.68446E+051.20461E+040.00000E+000.00000E+00 415 8457   18
1.54390E+061.80000E+03          0          0          6          0 415 8457   19
1.00000E+001.00000E+007.00000E-021.10000E-020.00000E+000.00000E+00 415 8457   20
2.15250E+061.70000E+03          0          0          6          0 415 8457   21
1.00000E+001.00000E+009.30000E-011.10000E-020.00000E+000.00000E+00 415 8457   22
0.00000E+008.00000E+00          0          0          6          6 415 8457   23
1.00000E+000.00000E+004.86711E+024.86711E+010.00000E+000.00000E+00 415 8457   24
2.93000E+011.46500E+00          0          0          6          0 415 8457   25
1.00000E+000.00000E+004.81206E-034.81206E-040.00000E+000.00000E+00 415 8457   26
4.50000E+022.25000E+01          0          0          6          0 415 8457   27
1.00000E+000.00000E+002.31285E-032.31285E-040.00000E+000.00000E+00 415 8457   28
4.52200E+032.26100E+02          0          0          6          0 415 8457   29
1.00000E+000.00000E+001.03994E-031.03994E-040.00000E+000.00000E+00 415 8457   30
3.14620E+051.57310E+04          0          0          6          0 415 8457   31
1.00000E+000.00000E+001.38474E-031.38474E-040.00000E+000.00000E+00 415 8457   32
3.19572E+051.59786E+04          0          0          6          0 415 8457   33
1.00000E+000.00000E+001.31880E-041.31880E-050.00000E+000.00000E+00 415 8457   34
3.20056E+051.60028E+04          0          0          6          0 415 8457   35
1.00000E+000.00000E+009.42000E-069.42000E-070.00000E+000.00000E+00 415 8457   36
0.00000E+009.00000E+00          0          0          6          3 415 8457   37
1.00000E+000.00000E+001.72626E+001.72626E-010.00000E+000.00000E+00 415 8457   38
4.94464E+039.88928E+01          0          0          6          0 415 8457   39
1.00000E+000.00000E+001.01864E-041.01864E-050.00000E+000.00000E+00 415 8457   40
4.95220E+039.90440E+01          0          0          6          0 415 8457   41
1.00000E+000.00000E+002.02110E-042.02110E-050.00000E+000.00000E+00 415 8457   42
5.43000E+031.08600E+02          0          0          6          0 415 8457   43
1.00000E+000.00000E+004.08263E-054.08263E-060.00000E+000.00000E+00 415 8457   44
                                                                   415 8  099999
                                                                   415 0  0    0
                                                                     0 0  0    0
 2.205200+4 5.150060+1         -1          0          2          1 416 1451    1
 0.000000+0 1.000000+0          0          0          0          6 416 1451    2
 0.000000+0 0.000000+0          0          0          4        311 416 1451    3
 0.000000+0 0.000000+0          0          0         44          2 416 1451    4
 22-Ti- 52 ENSDF      EVAL-MAY00 CONVERSION OF ENSDF               416 1451    5
 /ENSDF/              DIST-NOV07                       261107      416 1451    6
----JEFF-311          MATERIAL  416                                416 1451    7
-----RADIOACTIVE DECAY DATA                                        416 1451    8
------ENDF-6 FORMAT                                                416 1451    9
****************************************************************** 416 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 416 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 416 1451   12
**             Original data taken from:  ENSDF                 ** 416 1451   13
****************************************************************** 416 1451   14
****************************************************************** 416 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 416 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 416 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 416 1451   18
****************************************************************** 416 1451   19
52TI  DECAY 1.7 M     1                     I(min) = 0.0E+00 %     416 1451   20
         Ex = 0.0         keV                     1 decay mode(s)  416 1451   21
                                                                   416 1451   22
52TI B- DECAY               Q =  1973.0000 keV       7.0000        416 1451   23
         Branching                100.0000 %         0.0000        416 1451   24
                         Br*Q =  1973.0000 keV       7.0000        416 1451   25
                                              0 isomeric state(s)  416 1451   26
                                                                   416 1451   27
Individual beta- transitions                                       416 1451   28
Final level    end point    shape    av.energy        intensity    416 1451   29
  141.400   1831.525   7.006  0    742.000   4.000  100.000 0.000  416 1451   30
                                                                   416 1451   31
         Mean alpha    energy       0.0000 keV       0.0000        416 1451   32
         Mean beta     energy     742.0000 keV       4.0000        416 1451   33
         Mean conv. e- energy       9.7516 keV       3.0906        416 1451   34
         Mean Auger e- energy       2.8510 keV       0.8697        416 1451   35
         Mean gamma    energy     127.5405 keV                     416 1451   36
         Mean X        energy       0.8799 keV       0.2150        416 1451   37
         Mean recoil   energy       0.0749 keV       0.0003        416 1451   38
         Mean neutrino energy    1089.5252 keV       4.0000        416 1451   39
         Mean neutron  energy       0.0000 keV       0.0000        416 1451   40
         Total         energy    1972.6233 keV       6.5889        416 1451   41
         Q effective             1973.0000 keV       7.0000        416 1451   42
         diff. mode                -0.3767 keV      -0.0191 %      416 1451   43
                                                                   416 1451   44
         Mean e- bind. energy       3.8953 keV                     416 1451   45
         diff. atomic              -0.1644 keV      -4.2205 %      416 1451   46
         diff. nuclear             -0.2123 keV      -0.0108 %      416 1451   47
                                                                   416 1451   48
                                1        451         50          0 416 1451   49
                                8        457         37          0 416 1451   50
 0.000000+0 0.000000+0          0          0          0          0 416 1  099999
                                                                   416 0  0    0
 2.20520+04 5.15006+01          0          0          0          4 416 8457    1
 1.02000+02 6.00000+00          0          0          6          0 416 8457    2
 7.54603+05 5.12913+03 1.28420+05 1.05140+03 0.00000+00 0.00000+00 416 8457    3
 0.00000+00 1.00000+00          0          0          6          1 416 8457    4
 1.00000+00 0.00000+00 1.97300+06 7.00000+03 1.00000+00 0.00000+00 416 8457    5
 0.00000+00 0.00000+00          0          0          6          2 416 8457    6
 1.00000-02 0.00000+00 1.27541+05 1.02918+03 0.00000+00 0.00000+00 416 8457    7
 1.71530+04 6.00000+00          0          0         12          0 416 8457    8
 1.00000+00 0.00000+00 1.80000+01 6.00000+00 0.00000+00 0.00000+00 416 8457    9
 4.60000+00 1.80000+00 3.90000+00 6.11301-01 5.20000-01 1.30933-01 416 8457   10
 1.24453+05 3.00000+00          0          0         12          0 416 8457   11
 1.00000+00 0.00000+00 1.00000+02 0.00000+00 0.00000+00 0.00000+00 416 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 416 8457   13
 0.00000+00 1.00000+00          0          0          6          1 416 8457   14
 1.00000-02 0.00000+00 7.42000+05 4.00000+03 0.00000+00 0.00000+00 416 8457   15
 1.83153+06 7.00614+03          0          0          6          0 416 8457   16
 1.00000+00 1.00000+00 1.00000+02 0.00000+00 0.00000+00 0.00000+00 416 8457   17
 0.00000+00 8.00000+00          0          0          6          4 416 8457   18
 1.00000-02 0.00000+00 1.26026+04 3.21060+03 0.00000+00 0.00000+00 416 8457   19
 4.70000+02 0.00000+00          0          0          6          0 416 8457   20
 1.00000+00 0.00000+00 1.15937+02 3.94693+01 0.00000+00 0.00000+00 416 8457   21
 4.38000+03 0.00000+00          0          0          6          0 416 8457   22
 1.00000+00 0.00000+00 5.26500+01 1.93997+01 0.00000+00 0.00000+00 416 8457   23
 1.16879+04 6.00750+00          0          0          6          0 416 8457   24
 1.00000+00 0.00000+00 7.02000+01 2.58580+01 0.00000+00 0.00000+00 416 8457   25
 1.65248+04 6.01332+00          0          0          6          0 416 8457   26
 1.00000+00 0.00000+00 9.36000+00 3.91010+00 0.00000+00 0.00000+00 416 8457   27
 0.00000+00 9.00000+00          0          0          6          4 416 8457   28
 1.00000-02 0.00000+00 8.79925+02 2.15004+02 0.00000+00 0.00000+00 416 8457   29
 5.10000+02 0.00000+00          0          0          6          0 416 8457   30
 1.00000+00 0.00000+00 2.67270-01 1.30081-01 0.00000+00 0.00000+00 416 8457   31
 4.94464+03 4.00000-02          0          0          6          0 416 8457   32
 1.00000+00 0.00000+00 5.19075+00 1.91879+00 0.00000+00 0.00000+00 416 8457   33
 4.95220+03 4.00000-02          0          0          6          0 416 8457   34
 1.00000+00 0.00000+00 1.02991+01 3.80531+00 0.00000+00 0.00000+00 416 8457   35
 5.43000+03 0.00000+00          0          0          6          0 416 8457   36
 1.00000+00 0.00000+00 2.06015+00 7.62144-01 0.00000+00 0.00000+00 416 8457   37
                                                                   416 8  099999
                                                                   416 0  0    0
                                                                     0 0  0    0
 2.205300+4 5.249490+1         -1          0          2          1 417 1451    1
 0.000000+0 1.000000+0          0          0          0          6 417 1451    2
 0.000000+0 0.000000+0          0          0          4        311 417 1451    3
 0.000000+0 0.000000+0          0          0         18          2 417 1451    4
 22-Ti- 53 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  417 1451    5
                      DIST-NOV07                       261107      417 1451    6
----JEFF-311          MATERIAL  417                                417 1451    7
-----RADIOACTIVE DECAY DATA                                        417 1451    8
------ENDF-6 FORMAT                                                417 1451    9
****************************************************************** 417 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 417 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 417 1451   12
**             Original data taken from:  NUBASE                ** 417 1451   13
****************************************************************** 417 1451   14
****************************************************************** 417 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 417 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      417 1451   17
                                                                   417 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           417 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        417 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               417 1451   21
****************************************************************** 417 1451   22
                                1        451         24          0 417 1451   23
                                8        457          5          0 417 1451   24
 0.000000+0 0.000000+0          0          0          0          0 417 1  099999
                                                                   417 0  0    0
 2.20530+04 5.24949+01          0          0          0          0 417 8457    1
 3.27000+01 9.00000-01          0          0          6          0 417 8457    2
 1.67300+06 0.00000+00 1.67300+06 0.00000+00 0.00000+00 0.00000+00 417 8457    3
 1.50000+00-1.00000+00          0          0          6          1 417 8457    4
 1.00000+00 0.00000+00 5.01900+06 0.00000+00 1.00000+00 0.00000+00 417 8457    5
                                                                   417 8  099999
                                                                   417 0  0    0
                                                                     0 0  0    0
 2.205400+4 5.348760+1         -1          0          2          1 418 1451    1
 0.000000+0 1.000000+0          0          0          0          6 418 1451    2
 0.000000+0 0.000000+0          0          0          4        311 418 1451    3
 0.000000+0 0.000000+0          0          0         18          2 418 1451    4
 22-Ti- 54 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  418 1451    5
                      DIST-NOV07                       261107      418 1451    6
----JEFF-311          MATERIAL  418                                418 1451    7
-----RADIOACTIVE DECAY DATA                                        418 1451    8
------ENDF-6 FORMAT                                                418 1451    9
****************************************************************** 418 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 418 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 418 1451   12
**             Original data taken from:  NUBASE                ** 418 1451   13
****************************************************************** 418 1451   14
****************************************************************** 418 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 418 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      418 1451   17
                                                                   418 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           418 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        418 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               418 1451   21
****************************************************************** 418 1451   22
                                1        451         24          0 418 1451   23
                                8        457          5          0 418 1451   24
 0.000000+0 0.000000+0          0          0          0          0 418 1  099999
                                                                   418 0  0    0
 2.20540+04 5.34876+01          0          0          0          0 418 8457    1
 1.50000+00 4.00000-01          0          0          6          0 418 8457    2
 1.43367+06 0.00000+00 1.43367+06 0.00000+00 0.00000+00 0.00000+00 418 8457    3
 0.00000+00 1.00000+00          0          0          6          1 418 8457    4
 1.00000+00 0.00000+00 4.30100+06 0.00000+00 1.00000+00 0.00000+00 418 8457    5
                                                                   418 8  099999
                                                                   418 0  0    0
                                                                     0 0  0    0
 2.205500+4 5.448320+1         -1          0          2          1 419 1451    1
 0.000000+0 1.000000+0          0          0          0          6 419 1451    2
 0.000000+0 0.000000+0          0          0          4        311 419 1451    3
 0.000000+0 0.000000+0          0          0         18          2 419 1451    4
 22-Ti- 55 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  419 1451    5
                      DIST-NOV07                       261107      419 1451    6
----JEFF-311          MATERIAL  419                                419 1451    7
-----RADIOACTIVE DECAY DATA                                        419 1451    8
------ENDF-6 FORMAT                                                419 1451    9
****************************************************************** 419 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 419 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 419 1451   12
**             Original data taken from:  NUBASE                ** 419 1451   13
****************************************************************** 419 1451   14
****************************************************************** 419 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 419 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      419 1451   17
                                                                   419 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           419 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        419 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               419 1451   21
****************************************************************** 419 1451   22
                                1        451         24          0 419 1451   23
                                8        457          5          0 419 1451   24
 0.000000+0 0.000000+0          0          0          0          0 419 1  099999
                                                                   419 0  0    0
 2.20550+04 5.44832+01          0          0          0          0 419 8457    1
 4.90000-01 9.00000-02          0          0          6          0 419 8457    2
 2.49333+06 0.00000+00 2.49333+06 0.00000+00 0.00000+00 0.00000+00 419 8457    3
 1.50000+00-1.00000+00          0          0          6          1 419 8457    4
 1.00000+00 0.00000+00 7.48000+06 0.00000+00 1.00000+00 0.00000+00 419 8457    5
                                                                   419 8  099999
                                                                   419 0  0    0
                                                                     0 0  0    0
 2.205600+4 5.547750+1         -1          0          2          1 420 1451    1
 0.000000+0 1.000000+0          0          0          0          6 420 1451    2
 0.000000+0 0.000000+0          0          0          4        311 420 1451    3
 0.000000+0 0.000000+0          0          0         18          2 420 1451    4
 22-Ti- 56 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  420 1451    5
                      DIST-NOV07                       261107      420 1451    6
----JEFF-311          MATERIAL  420                                420 1451    7
-----RADIOACTIVE DECAY DATA                                        420 1451    8
------ENDF-6 FORMAT                                                420 1451    9
****************************************************************** 420 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 420 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 420 1451   12
**             Original data taken from:  NUBASE                ** 420 1451   13
****************************************************************** 420 1451   14
****************************************************************** 420 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 420 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      420 1451   17
                                                                   420 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           420 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        420 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               420 1451   21
****************************************************************** 420 1451   22
                                1        451         24          0 420 1451   23
                                8        457          5          0 420 1451   24
 0.000000+0 0.000000+0          0          0          0          0 420 1  099999
                                                                   420 0  0    0
 2.20560+04 5.54775+01          0          0          0          0 420 8457    1
 1.64000-01 2.40000-02          0          0          6          0 420 8457    2
 2.38000+06 0.00000+00 2.38000+06 0.00000+00 0.00000+00 0.00000+00 420 8457    3
 0.00000+00 1.00000+00          0          0          6          1 420 8457    4
 1.00000+00 0.00000+00 7.14000+06 0.00000+00 1.00000+00 0.00000+00 420 8457    5
                                                                   420 8  099999
                                                                   420 0  0    0
                                                                     0 0  0    0
 2.205700+4 5.647460+1         -1          0          2          1 421 1451    1
 0.000000+0 1.000000+0          0          0          0          6 421 1451    2
 0.000000+0 0.000000+0          0          0          4        311 421 1451    3
 0.000000+0 0.000000+0          0          0         18          2 421 1451    4
 22-Ti- 57 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  421 1451    5
                      DIST-NOV07                       261107      421 1451    6
----JEFF-311          MATERIAL  421                                421 1451    7
-----RADIOACTIVE DECAY DATA                                        421 1451    8
------ENDF-6 FORMAT                                                421 1451    9
****************************************************************** 421 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 421 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 421 1451   12
**             Original data taken from:  NUBASE                ** 421 1451   13
****************************************************************** 421 1451   14
****************************************************************** 421 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 421 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      421 1451   17
                                                                   421 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           421 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        421 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               421 1451   21
****************************************************************** 421 1451   22
                                1        451         24          0 421 1451   23
                                8        457          6          0 421 1451   24
 0.000000+0 0.000000+0          0          0          0          0 421 1  099999
                                                                   421 0  0    0
 2.20570+04 5.64746+01          0          0          0          0 421 8457    1
 6.00000-02 1.60000-02          0          0          6          0 421 8457    2
 3.54270+06 0.00000+00 3.54270+06 0.00000+00 3.35153+03 0.00000+00 421 8457    3
 2.50000+00-1.00000+00          0          0         12          2 421 8457    4
 1.00000+00 0.00000+00 1.06500+07 0.00000+00 9.97000-01 0.00000+00 421 8457    5
 1.50000+00 0.00000+00 4.46870+06 0.00000+00 3.00000-03 0.00000+00 421 8457    6
                                                                   421 8  099999
                                                                   421 0  0    0
                                                                     0 0  0    0
 2.205800+4 5.746900+1         -1          0          2          1 422 1451    1
 0.000000+0 1.000000+0          0          0          0          6 422 1451    2
 0.000000+0 0.000000+0          0          0          4        311 422 1451    3
 0.000000+0 0.000000+0          0          0         18          2 422 1451    4
 22-Ti- 58 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  422 1451    5
                      DIST-NOV07                       261107      422 1451    6
----JEFF-311          MATERIAL  422                                422 1451    7
-----RADIOACTIVE DECAY DATA                                        422 1451    8
------ENDF-6 FORMAT                                                422 1451    9
****************************************************************** 422 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 422 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 422 1451   12
**             Original data taken from:  NUBASE                ** 422 1451   13
****************************************************************** 422 1451   14
****************************************************************** 422 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 422 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      422 1451   17
                                                                   422 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           422 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        422 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               422 1451   21
****************************************************************** 422 1451   22
                                1        451         24          0 422 1451   23
                                8        457          5          0 422 1451   24
 0.000000+0 0.000000+0          0          0          0          0 422 1  099999
                                                                   422 0  0    0
 2.20580+04 5.74690+01          0          0          0          0 422 8457    1
 5.40000-02 7.00000-03          0          0          6          0 422 8457    2
 3.14667+06 0.00000+00 3.14667+06 0.00000+00 0.00000+00 0.00000+00 422 8457    3
 0.00000+00 1.00000+00          0          0          6          1 422 8457    4
 1.00000+00 0.00000+00 9.44000+06 0.00000+00 1.00000+00 0.00000+00 422 8457    5
                                                                   422 8  099999
                                                                   422 0  0    0
                                                                     0 0  0    0
 2.205900+4 5.846630+1         -1          0          2          1 423 1451    1
 0.000000+0 1.000000+0          0          0          0          6 423 1451    2
 0.000000+0 0.000000+0          0          0          4        311 423 1451    3
 0.000000+0 0.000000+0          0          0         18          2 423 1451    4
 22-Ti- 59 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  423 1451    5
                      DIST-NOV07                       261107      423 1451    6
----JEFF-311          MATERIAL  423                                423 1451    7
-----RADIOACTIVE DECAY DATA                                        423 1451    8
------ENDF-6 FORMAT                                                423 1451    9
****************************************************************** 423 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 423 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 423 1451   12
**             Original data taken from:  NUBASE                ** 423 1451   13
****************************************************************** 423 1451   14
****************************************************************** 423 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 423 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      423 1451   17
                                                                   423 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           423 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        423 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               423 1451   21
****************************************************************** 423 1451   22
                                1        451         24          0 423 1451   23
                                8        457          5          0 423 1451   24
 0.000000+0 0.000000+0          0          0          0          0 423 1  099999
                                                                   423 0  0    0
 2.20590+04 5.84663+01          0          0          0          0 423 8457    1
 3.00000-02 2.50000-03          0          0          6          0 423 8457    2
 3.95000+06 0.00000+00 3.95000+06 0.00000+00 0.00000+00 0.00000+00 423 8457    3
 2.50000+00-1.00000+00          0          0          6          1 423 8457    4
 1.00000+00 0.00000+00 1.18500+07 0.00000+00 1.00000+00 0.00000+00 423 8457    5
                                                                   423 8  099999
                                                                   423 0  0    0
                                                                     0 0  0    0
 2.206000+4 5.946150+1         -1          0          2          1 424 1451    1
 0.000000+0 1.000000+0          0          0          0          6 424 1451    2
 0.000000+0 0.000000+0          0          0          4        311 424 1451    3
 0.000000+0 0.000000+0          0          0         18          2 424 1451    4
 22-Ti- 60 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  424 1451    5
                      DIST-NOV07                       261107      424 1451    6
----JEFF-311          MATERIAL  424                                424 1451    7
-----RADIOACTIVE DECAY DATA                                        424 1451    8
------ENDF-6 FORMAT                                                424 1451    9
****************************************************************** 424 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 424 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 424 1451   12
**             Original data taken from:  NUBASE                ** 424 1451   13
****************************************************************** 424 1451   14
****************************************************************** 424 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 424 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      424 1451   17
                                                                   424 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           424 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        424 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               424 1451   21
****************************************************************** 424 1451   22
                                1        451         24          0 424 1451   23
                                8        457          5          0 424 1451   24
 0.000000+0 0.000000+0          0          0          0          0 424 1  099999
                                                                   424 0  0    0
 2.20600+04 5.94615+01          0          0          0          0 424 8457    1
 2.20000-02 2.00000-03          0          0          6          0 424 8457    2
 3.64333+06 0.00000+00 3.64333+06 0.00000+00 0.00000+00 0.00000+00 424 8457    3
 0.00000+00 1.00000+00          0          0          6          1 424 8457    4
 1.00000+00 0.00000+00 1.09300+07 0.00000+00 1.00000+00 0.00000+00 424 8457    5
                                                                   424 8  099999
                                                                   424 0  0    0
                                                                     0 0  0    0
 2.206100+4 6.045930+1         -1          0          2          1 425 1451    1
 0.000000+0 1.000000+0          0          0          0          6 425 1451    2
 0.000000+0 0.000000+0          0          0          4        311 425 1451    3
 0.000000+0 0.000000+0          0          0         18          2 425 1451    4
 22-Ti- 61 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  425 1451    5
                      DIST-NOV07                       261107      425 1451    6
----JEFF-311          MATERIAL  425                                425 1451    7
-----RADIOACTIVE DECAY DATA                                        425 1451    8
------ENDF-6 FORMAT                                                425 1451    9
****************************************************************** 425 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 425 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 425 1451   12
**             Original data taken from:  NUBASE                ** 425 1451   13
****************************************************************** 425 1451   14
****************************************************************** 425 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 425 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      425 1451   17
                                                                   425 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           425 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        425 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               425 1451   21
****************************************************************** 425 1451   22
                                1        451         24          0 425 1451   23
                                8        457          5          0 425 1451   24
 0.000000+0 0.000000+0          0          0          0          0 425 1  099999
                                                                   425 0  0    0
 2.20610+04 6.04593+01          0          0          0          0 425 8457    1
 1.00000-02 0.00000+00          0          0          6          0 425 8457    2
 4.57000+06 0.00000+00 4.57000+06 0.00000+00 0.00000+00 0.00000+00 425 8457    3
 5.00000-01-1.00000+00          0          0          6          1 425 8457    4
 1.00000+00 0.00000+00 1.37100+07 0.00000+00 1.00000+00 0.00000+00 425 8457    5
                                                                   425 8  099999
                                                                   425 0  0    0
                                                                     0 0  0    0
 2.206200+4 6.145500+1         -1          0          2          1 426 1451    1
 0.000000+0 1.000000+0          0          0          0          6 426 1451    2
 0.000000+0 0.000000+0          0          0          4        311 426 1451    3
 0.000000+0 0.000000+0          0          0         18          2 426 1451    4
 22-Ti- 62 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  426 1451    5
                      DIST-NOV07                       261107      426 1451    6
----JEFF-311          MATERIAL  426                                426 1451    7
-----RADIOACTIVE DECAY DATA                                        426 1451    8
------ENDF-6 FORMAT                                                426 1451    9
****************************************************************** 426 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 426 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 426 1451   12
**             Original data taken from:  NUBASE                ** 426 1451   13
****************************************************************** 426 1451   14
****************************************************************** 426 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 426 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      426 1451   17
                                                                   426 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           426 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        426 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               426 1451   21
****************************************************************** 426 1451   22
                                1        451         24          0 426 1451   23
                                8        457          5          0 426 1451   24
 0.000000+0 0.000000+0          0          0          0          0 426 1  099999
                                                                   426 0  0    0
 2.20620+04 6.14550+01          0          0          0          0 426 8457    1
 1.00000-02 0.00000+00          0          0          6          0 426 8457    2
 4.25667+06 0.00000+00 4.25667+06 0.00000+00 0.00000+00 0.00000+00 426 8457    3
 0.00000+00 1.00000+00          0          0          6          1 426 8457    4
 1.00000+00 0.00000+00 1.27700+07 0.00000+00 1.00000+00 0.00000+00 426 8457    5
                                                                   426 8  099999
                                                                   426 0  0    0
                                                                     0 0  0    0
 2.206300+4 6.245330+1         -1          0          2          1 427 1451    1
 0.000000+0 1.000000+0          0          0          0          6 427 1451    2
 0.000000+0 0.000000+0          0          0          4        311 427 1451    3
 0.000000+0 0.000000+0          0          0         18          2 427 1451    4
 22-Ti- 63 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  427 1451    5
                      DIST-NOV07                       261107      427 1451    6
----JEFF-311          MATERIAL  427                                427 1451    7
-----RADIOACTIVE DECAY DATA                                        427 1451    8
------ENDF-6 FORMAT                                                427 1451    9
****************************************************************** 427 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 427 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 427 1451   12
**             Original data taken from:  NUBASE                ** 427 1451   13
****************************************************************** 427 1451   14
****************************************************************** 427 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 427 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      427 1451   17
                                                                   427 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           427 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        427 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               427 1451   21
****************************************************************** 427 1451   22
                                1        451         24          0 427 1451   23
                                8        457          5          0 427 1451   24
 0.000000+0 0.000000+0          0          0          0          0 427 1  099999
                                                                   427 0  0    0
 2.20630+04 6.24533+01          0          0          0          0 427 8457    1
 3.00000-03 0.00000+00          0          0          6          0 427 8457    2
 5.23667+06 0.00000+00 5.23667+06 0.00000+00 0.00000+00 0.00000+00 427 8457    3
 5.00000-01-1.00000+00          0          0          6          1 427 8457    4
 1.00000+00 0.00000+00 1.57100+07 0.00000+00 1.00000+00 0.00000+00 427 8457    5
                                                                   427 8  099999
                                                                   427 0  0    0
                                                                     0 0  0    0
