 1.502400+4 2.382790+1         -1          0          2          1 226 1451    1
 0.000000+0 1.000000+0          0          0          0          6 226 1451    2
 0.000000+0 0.000000+0          0          0          4        311 226 1451    3
 0.000000+0 0.000000+0          0          0         18          2 226 1451    4
 15-P - 24 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  226 1451    5
                      DIST-NOV07                       261107      226 1451    6
----JEFF-311          MATERIAL  226                                226 1451    7
-----RADIOACTIVE DECAY DATA                                        226 1451    8
------ENDF-6 FORMAT                                                226 1451    9
****************************************************************** 226 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 226 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 226 1451   12
**             Original data taken from:  NUBASE                ** 226 1451   13
****************************************************************** 226 1451   14
****************************************************************** 226 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 226 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      226 1451   17
                                                                   226 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           226 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        226 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               226 1451   21
****************************************************************** 226 1451   22
                                1        451         24          0 226 1451   23
                                8        457          6          0 226 1451   24
 0.000000+0 0.000000+0          0          0          0          0 226 1  099999
                                                                   226 0  0    0
 1.50240+04 2.38279+01          0          0          0          0 226 8457    1
 1.00000-09 1.00000-09          0          0          6          0 226 8457    2
 3.54083+06 0.00000+00 3.54083+06 0.00000+00 4.70500+05 0.00000+00 226 8457    3
 1.00000+00 1.00000+00          0          0         12          2 226 8457    4
 7.00000+00 0.00000+00 9.41000+05 0.00000+00 5.00000-01 0.00000+00 226 8457    5
 2.00000+00 0.00000+00 2.12450+07 0.00000+00 5.00000-01 0.00000+00 226 8457    6
                                                                   226 8  099999
                                                                   226 0  0    0
                                                                     0 0  0    0
 1.502500+4 2.480530+1         -1          0          2          1 227 1451    1
 0.000000+0 1.000000+0          0          0          0          6 227 1451    2
 0.000000+0 0.000000+0          0          0          4        311 227 1451    3
 0.000000+0 0.000000+0          0          0         18          2 227 1451    4
 15-P - 25 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  227 1451    5
                      DIST-NOV07                       261107      227 1451    6
----JEFF-311          MATERIAL  227                                227 1451    7
-----RADIOACTIVE DECAY DATA                                        227 1451    8
------ENDF-6 FORMAT                                                227 1451    9
****************************************************************** 227 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 227 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 227 1451   12
**             Original data taken from:  NUBASE                ** 227 1451   13
****************************************************************** 227 1451   14
****************************************************************** 227 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 227 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      227 1451   17
                                                                   227 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           227 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        227 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               227 1451   21
****************************************************************** 227 1451   22
                                1        451         24          0 227 1451   23
                                8        457          5          0 227 1451   24
 0.000000+0 0.000000+0          0          0          0          0 227 1  099999
                                                                   227 0  0    0
 1.50250+04 2.48053+01          0          0          0          0 227 8457    1
 3.00000-08 0.00000+00          0          0          6          0 227 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 8.26001+05 0.00000+00 227 8457    3
 5.00000-01 1.00000+00          0          0          6          1 227 8457    4
 7.00000+00 0.00000+00 8.26001+05 0.00000+00 1.00000+00 0.00000+00 227 8457    5
                                                                   227 8  099999
                                                                   227 0  0    0
                                                                     0 0  0    0
 1.502600+4 2.578830+1         -1          0          2          1 228 1451    1
 0.000000+0 1.000000+0          0          0          0          6 228 1451    2
 0.000000+0 0.000000+0          0          0          4        311 228 1451    3
 0.000000+0 0.000000+0          0          0         18          2 228 1451    4
 15-P - 26 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  228 1451    5
                      DIST-NOV07                       261107      228 1451    6
----JEFF-311          MATERIAL  228                                228 1451    7
-----RADIOACTIVE DECAY DATA                                        228 1451    8
------ENDF-6 FORMAT                                                228 1451    9
****************************************************************** 228 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 228 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 228 1451   12
**             Original data taken from:  NUBASE                ** 228 1451   13
****************************************************************** 228 1451   14
****************************************************************** 228 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 228 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      228 1451   17
                                                                   228 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           228 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        228 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               228 1451   21
****************************************************************** 228 1451   22
                                1        451         24          0 228 1451   23
                                8        457          7          0 228 1451   24
 0.000000+0 0.000000+0          0          0          0          0 228 1  099999
                                                                   228 0  0    0
 1.50260+04 2.57883+01          0          0          0          0 228 8457    1
 3.00000-02 2.50000-02          0          0          6          0 228 8457    2
 5.97776+06 0.00000+00 5.97776+06 0.00000+00 5.41576+04 0.00000+00 228 8457    3
 3.00000+00 1.00000+00          0          0         18          3 228 8457    4
 2.00000+00 0.00000+00 1.81150+07 0.00000+00 9.81000-01 0.00000+00 228 8457    5
 2.77000+00 0.00000+00 1.03256+07 0.00000+00 1.00000-02 0.00000+00 228 8457    6
 2.70000+00 0.00000+00 1.25972+07 0.00000+00 9.00000-03 0.00000+00 228 8457    7
                                                                   228 8  099999
                                                                   228 0  0    0
                                                                     0 0  0    0
 1.502700+4 2.676730+1         -1          0          2          1 229 1451    1
 0.000000+0 1.000000+0          0          0          0          6 229 1451    2
 0.000000+0 0.000000+0          0          0          4        311 229 1451    3
 0.000000+0 0.000000+0          0          0         18          2 229 1451    4
 15-P - 27 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  229 1451    5
                      DIST-NOV07                       261107      229 1451    6
----JEFF-311          MATERIAL  229                                229 1451    7
-----RADIOACTIVE DECAY DATA                                        229 1451    8
------ENDF-6 FORMAT                                                229 1451    9
****************************************************************** 229 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 229 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 229 1451   12
**             Original data taken from:  NUBASE                ** 229 1451   13
****************************************************************** 229 1451   14
****************************************************************** 229 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 229 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      229 1451   17
                                                                   229 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           229 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        229 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               229 1451   21
****************************************************************** 229 1451   22
                                1        451         24          0 229 1451   23
                                8        457          6          0 229 1451   24
 0.000000+0 0.000000+0          0          0          0          0 229 1  099999
                                                                   229 0  0    0
 1.50270+04 2.67673+01          0          0          0          0 229 8457    1
 2.60000-01 8.00000-02          0          0          6          0 229 8457    2
 3.88707+06 0.00000+00 3.88707+06 0.00000+00 6.95801+02 0.00000+00 229 8457    3
 5.00000-01 1.00000+00          0          0         12          2 229 8457    4
 2.00000+00 0.00000+00 1.16673+07 0.00000+00 9.99300-01 0.00000+00 229 8457    5
 2.70000+00 1.00000+00 3.97601+06 0.00000+00 7.00000-04 0.00000+00 229 8457    6
                                                                   229 8  099999
                                                                   229 0  0    0
                                                                     0 0  0    0
 1.502800+4 2.775180+1         -1          0          2          1 230 1451    1
 0.000000+0 1.000000+0          0          0          0          6 230 1451    2
 0.000000+0 0.000000+0          0          0          4        311 230 1451    3
 0.000000+0 0.000000+0          0          0         71          2 230 1451    4
 15-P - 28 ENSDF      EVAL-MAR01 CONVERSION OF ENSDF               230 1451    5
 /ENSDF/              DIST-NOV07                       261107      230 1451    6
----JEFF-311          MATERIAL  230                                230 1451    7
-----RADIOACTIVE DECAY DATA                                        230 1451    8
------ENDF-6 FORMAT                                                230 1451    9
****************************************************************** 230 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 230 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 230 1451   12
**             Original data taken from:  ENSDF                 ** 230 1451   13
****************************************************************** 230 1451   14
****************************************************************** 230 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 230 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 230 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 230 1451   18
****************************************************************** 230 1451   19
28P   DECAY 270.3 MS  5                     I(min) = 0.0E+00 %     230 1451   20
         Ex = 0.0         keV                     1 decay mode(s)  230 1451   21
                                                                   230 1451   22
28P EC DECAY                Q = 14332.0000 keV       4.0000        230 1451   23
         Branching                100.0000 %         0.0000        230 1451   24
                         Br*Q = 14332.0000 keV       4.0000        230 1451   25
                                              0 isomeric state(s)  230 1451   26
                                                                   230 1451   27
Individual beta+ transitions                                       230 1451   28
Final level    end point    shape    av.energy        intensity    230 1451   29
13093.100    216.783   4.009  0     87.100   1.600    0.000 0.000  230 1451   30
12899.400    410.376   4.009  0    164.300   1.600    0.000 0.000  230 1451   31
12725.300    584.380   4.009  0    235.900   1.700    0.000 0.000  230 1451   32
12714.200    595.474   4.009  1    240.500   1.700    0.000 0.000  230 1451   33
12572.900    736.697   4.009  0    300.100   1.700    0.000 0.000  230 1451   34
12550.300    759.284   4.009  0    309.700   1.700    0.000 0.000  230 1451   35
12440.300    869.224   4.009  0    356.600   1.700    0.001 0.000  230 1451   36
12289.500   1019.941   4.009  0    422.300   1.800    0.001 0.000  230 1451   37
12071.300   1238.021   4.009  0    519.300   1.800    0.000 0.000  230 1451   38
11931.000   1378.244   4.470  0    582.200   2.000    0.001 0.000  230 1451   39
11656.600   1652.493   4.029  0    707.100   1.800    0.000 0.000  230 1451   40
11515.300   1793.715   4.018  0    772.100   1.900    0.000 0.000  230 1451   41
10668.000   2640.550   6.400  0   1170.000   3.000    0.299 0.010  230 1451   42
10209.010   3099.287   4.003  0   1388.600   1.900    0.029 0.004  230 1451   43
 9795.950   3512.120   4.000  0   1587.300   1.900    0.053 0.007  230 1451   44
 9480.400   3827.497   4.270  0   1739.900   2.100    0.065 0.007  230 1451   45
 9381.200   3926.642   4.043  0   1788.000   2.000    0.590 0.030  230 1451   46
 9316.100   3991.706   4.029  0   1819.600   2.000   11.300 0.400  230 1451   47
 8588.900   4718.507   4.043  0   2173.700   2.000    3.640 0.110  230 1451   48
 8259.400   5047.825   4.043  0   2334.900   2.000    0.537 0.011  230 1451   49
 7933.400   5373.646   4.018  0   2494.700   2.000    2.840 0.200  230 1451   50
 7798.800   5508.172   4.018  0   2560.800   2.000    2.440 0.090  230 1451   51
 7416.200   5890.562   3.999  0   2748.800   2.000    0.190 0.060  230 1451   52
 6276.500   7029.635   4.003  0   3310.600   2.000    7.600 0.400  230 1451   53
 4617.800   8687.424   4.003  0   4131.700   2.000    1.290 0.180  230 1451   54
 1778.980  11524.683   3.999  0   5542.400   2.000   69.100 0.700  230 1451   55
                                                                   230 1451   56
         Mean alpha    energy       0.0000 keV       0.0000        230 1451   57
         Mean beta     energy    4586.9734 keV      42.7770        230 1451   58
         Mean conv. e- energy       0.0000 keV       0.0000        230 1451   59
         Mean Auger e- energy       0.0000 keV       0.0000        230 1451   60
         Mean gamma    energy    4728.5424 keV                     230 1451   61
         Mean X        energy       0.0000 keV       0.0000        230 1451   62
         Mean recoil   energy       5.2771 keV       0.0492        230 1451   63
         Mean neutrino energy    5008.3914 keV      46.6665        230 1451   64
         Mean neutron  energy       0.0000 keV       0.0000        230 1451   65
         Total         energy   14329.4748 keV      71.2972        230 1451   66
         Q effective            14332.0000 keV       4.0000        230 1451   67
         diff. mode                -2.5252 keV      -0.0176 %      230 1451   68
                                                                   230 1451   69
         Mean e- bind. energy       0.0000 keV                     230 1451   70
         diff. atomic               0.0000 keV       0.0000 %      230 1451   71
         diff. nuclear             -2.5252 keV      -0.0176 %      230 1451   72
                                                                   230 1451   73
         B+ fraction               99.9767 %         0.9526        230 1451   74
                                                                   230 1451   75
                                1        451         77          0 230 1451   76
                                8        457        227          0 230 1451   77
 0.000000+0 0.000000+0          0          0          0          0 230 1  099999
                                                                   230 0  0    0
 1.50280+04 2.77518+01          0          0          0          3 230 8457    1
 2.70300-01 5.00000-04          0          0          6          0 230 8457    2
 4.58697+06 4.27770+04 4.72854+06 3.27972+04 5.27712+03 4.91575+01 230 8457    3
 3.00000+00 1.00000+00          0          0          6          1 230 8457    4
 2.00000+00 0.00000+00 1.43320+07 4.00000+03 1.00000+00 0.00000+00 230 8457    5
 0.00000+00 0.00000+00          0          0          6         54 230 8457    6
 1.00000-02 0.00000+00 3.70678+06 3.13189+04 0.00000+00 0.00000+00 230 8457    7
 6.11440+05 1.30000+02          0          0         12          0 230 8457    8
 2.00000+00 0.00000+00 2.00000-04 2.00000-04 0.00000+00 0.00000+00 230 8457    9
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   10
 9.11340+05 1.40000+02          0          0         12          0 230 8457   11
 2.00000+00 0.00000+00 4.00000-03 0.00000+00 0.00000+00 0.00000+00 230 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   13
 1.35220+06 2.00000+02          0          0         12          0 230 8457   14
 2.00000+00 0.00000+00 1.40000-01 2.00000-03 0.00000+00 0.00000+00 230 8457   15
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   16
 1.51650+06 5.00000+02          0          0         12          0 230 8457   17
 2.00000+00 0.00000+00 2.04000-01 1.40000-02 0.00000+00 0.00000+00 230 8457   18
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   19
 1.52279+06 9.00000+01          0          0         12          0 230 8457   20
 2.00000+00 0.00000+00 8.60000-01 3.00000-02 0.00000+00 0.00000+00 230 8457   21
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   22
 1.65710+06 3.00000+02          0          0         12          0 230 8457   23
 2.00000+00 0.00000+00 4.00000-01 1.70000-01 0.00000+00 0.00000+00 230 8457   24
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   25
 1.65881+06 0.00000+00          0          0         12          0 230 8457   26
 2.00000+00 0.00000+00 8.00000-01 1.70000-01 0.00000+00 0.00000+00 230 8457   27
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   28
 1.77897+06 1.10000+01          0          0         12          0 230 8457   29
 2.00000+00 0.00000+00 9.75000+01 5.00000-01 0.00000+00 0.00000+00 230 8457   30
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   31
 2.06314+06 1.50000+02          0          0         12          0 230 8457   32
 2.00000+00 0.00000+00 3.00000-04 0.00000+00 0.00000+00 0.00000+00 230 8457   33
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   34
 2.09829+06 0.00000+00          0          0         12          0 230 8457   35
 2.00000+00 0.00000+00 4.00000-04 0.00000+00 0.00000+00 0.00000+00 230 8457   36
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   37
 2.26083+06 9.00000+01          0          0         12          0 230 8457   38
 2.00000+00 0.00000+00 1.50000-04 1.50000-04 0.00000+00 0.00000+00 230 8457   39
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   40
 2.26969+06 1.10000+02          0          0         12          0 230 8457   41
 2.00000+00 0.00000+00 2.50000-04 2.50000-04 0.00000+00 0.00000+00 230 8457   42
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   43
 2.31230+06 1.00000+02          0          0         12          0 230 8457   44
 2.00000+00 0.00000+00 1.96000-01 6.00000-03 0.00000+00 0.00000+00 230 8457   45
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   46
 2.40055+06 1.30000+02          0          0         12          0 230 8457   47
 2.00000+00 0.00000+00 5.00000-05 5.00000-05 0.00000+00 0.00000+00 230 8457   48
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   49
 2.73420+06 0.00000+00          0          0         12          0 230 8457   50
 2.00000+00 0.00000+00 3.00000-03 0.00000+00 0.00000+00 0.00000+00 230 8457   51
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   52
 2.83829+06 1.50000+02          0          0         12          0 230 8457   53
 2.00000+00 0.00000+00 2.35000+00 5.00000-02 0.00000+00 0.00000+00 230 8457   54
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   55
 2.95340+06 2.00000+02          0          0         12          0 230 8457   56
 2.00000+00 0.00000+00 8.10000-02 3.00000-03 0.00000+00 0.00000+00 230 8457   57
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   58
 3.03920+06 2.00000+02          0          0         12          0 230 8457   59
 2.00000+00 0.00000+00 2.70000+00 7.00000-02 0.00000+00 0.00000+00 230 8457   60
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   61
 3.10460+06 3.00000+02          0          0         12          0 230 8457   62
 2.00000+00 0.00000+00 2.40000-02 4.00000-03 0.00000+00 0.00000+00 230 8457   63
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   64
 3.18150+06 2.00000+02          0          0         12          0 230 8457   65
 2.00000+00 0.00000+00 3.20000-02 3.00000-03 0.00000+00 0.00000+00 230 8457   66
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   67
 3.20070+06 5.00000+02          0          0         12          0 230 8457   68
 2.00000+00 0.00000+00 1.86000-01 9.00000-03 0.00000+00 0.00000+00 230 8457   69
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   70
 3.25190+06 5.00000+02          0          0         12          0 230 8457   71
 2.00000+00 0.00000+00 3.20000-02 3.00000-03 0.00000+00 0.00000+00 230 8457   72
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   73
 3.27880+06 4.00000+02          0          0         12          0 230 8457   74
 2.00000+00 0.00000+00 9.80000-02 4.00000-03 0.00000+00 0.00000+00 230 8457   75
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   76
 3.28725+06 1.70000+02          0          0         12          0 230 8457   77
 2.00000+00 0.00000+00 6.00000-03 0.00000+00 0.00000+00 0.00000+00 230 8457   78
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   79
 3.31580+06 2.00000+02          0          0         12          0 230 8457   80
 2.00000+00 0.00000+00 1.01000-01 6.00000-03 0.00000+00 0.00000+00 230 8457   81
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   82
 3.64123+06 0.00000+00          0          0         12          0 230 8457   83
 2.00000+00 0.00000+00 2.00000-03 0.00000+00 0.00000+00 0.00000+00 230 8457   84
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   85
 3.78012+06 1.60000+02          0          0         12          0 230 8457   86
 2.00000+00 0.00000+00 2.00000-02 0.00000+00 0.00000+00 0.00000+00 230 8457   87
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   88
 3.97090+06 2.00000+02          0          0         12          0 230 8457   89
 2.00000+00 0.00000+00 1.16000-01 2.40000-02 0.00000+00 0.00000+00 230 8457   90
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   91
 4.39127+06 0.00000+00          0          0         12          0 230 8457   92
 2.00000+00 0.00000+00 1.50000-02 0.00000+00 0.00000+00 0.00000+00 230 8457   93
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   94
 4.49692+06 2.50000+02          0          0         12          0 230 8457   95
 2.00000+00 0.00000+00 1.10000+01 3.00000-01 0.00000+00 0.00000+00 230 8457   96
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457   97
 4.49918+06 1.40000+02          0          0         12          0 230 8457   98
 2.00000+00 0.00000+00 3.00000-03 0.00000+00 0.00000+00 0.00000+00 230 8457   99
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  100
 4.86117+06 1.20000+02          0          0         12          0 230 8457  101
 2.00000+00 0.00000+00 4.00000-03 0.00000+00 0.00000+00 0.00000+00 230 8457  102
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  103
 5.09926+06 9.00000+01          0          0         12          0 230 8457  104
 2.00000+00 0.00000+00 2.50000-03 2.50000-03 0.00000+00 0.00000+00 230 8457  105
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  106
 5.10811+06 1.10000+02          0          0         12          0 230 8457  107
 2.00000+00 0.00000+00 2.10000-02 2.10000-02 0.00000+00 0.00000+00 230 8457  108
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  109
 5.60095+06 1.00000+02          0          0         12          0 230 8457  110
 2.00000+00 0.00000+00 1.35000-02 1.35000-02 0.00000+00 0.00000+00 230 8457  111
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  112
 5.63662+06 1.00000+02          0          0         12          0 230 8457  113
 2.00000+00 0.00000+00 1.00000-02 0.00000+00 0.00000+00 0.00000+00 230 8457  114
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  115
 6.01950+06 1.00000+02          0          0         12          0 230 8457  116
 2.00000+00 0.00000+00 1.75000+00 8.00000-02 0.00000+00 0.00000+00 230 8457  117
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  118
 6.15380+06 2.00000+02          0          0         12          0 230 8457  119
 2.00000+00 0.00000+00 1.12000-01 1.00000-02 0.00000+00 0.00000+00 230 8457  120
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  121
 6.47920+06 2.00000+02          0          0         12          0 230 8457  122
 2.00000+00 0.00000+00 3.85000-01 8.00000-03 0.00000+00 0.00000+00 230 8457  123
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  124
 6.80890+06 2.00000+02          0          0         12          0 230 8457  125
 2.00000+00 0.00000+00 3.33000+00 1.10000-01 0.00000+00 0.00000+00 230 8457  126
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  127
 6.87788+06 8.00000+01          0          0         12          0 230 8457  128
 2.00000+00 0.00000+00 4.50000-03 4.50000-03 0.00000+00 0.00000+00 230 8457  129
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  130
 7.37954+06 1.00000+02          0          0         12          0 230 8457  131
 2.00000+00 0.00000+00 7.50000-03 7.50000-03 0.00000+00 0.00000+00 230 8457  132
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  133
 7.41492+06 5.00000+01          0          0         12          0 230 8457  134
 2.00000+00 0.00000+00 2.10000-01 6.00000-02 0.00000+00 0.00000+00 230 8457  135
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  136
 7.53570+06 2.00000+02          0          0         12          0 230 8457  137
 2.00000+00 0.00000+00 8.50000+00 3.00000-01 0.00000+00 0.00000+00 230 8457  138
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  139
 7.60100+06 3.00000+02          0          0         12          0 230 8457  140
 2.00000+00 0.00000+00 5.50000-01 3.00000-02 0.00000+00 0.00000+00 230 8457  141
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  142
 7.69932+06 1.20000+02          0          0         12          0 230 8457  143
 2.00000+00 0.00000+00 2.00000-03 0.00000+00 0.00000+00 0.00000+00 230 8457  144
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  145
 7.93240+06 2.00000+02          0          0         12          0 230 8457  146
 2.00000+00 0.00000+00 2.15000+00 1.10000-01 0.00000+00 0.00000+00 230 8457  147
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  148
 8.01530+06 1.00000+03          0          0         12          0 230 8457  149
 2.00000+00 0.00000+00 4.00000-02 6.00000-03 0.00000+00 0.00000+00 230 8457  150
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  151
 8.25780+06 4.00000+02          0          0         12          0 230 8457  152
 2.00000+00 0.00000+00 5.20000-02 6.00000-03 0.00000+00 0.00000+00 230 8457  153
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  154
 8.42840+06 2.00000+02          0          0         12          0 230 8457  155
 2.00000+00 0.00000+00 2.90000-02 4.00000-03 0.00000+00 0.00000+00 230 8457  156
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  157
 8.88750+06 2.00000+02          0          0         12          0 230 8457  158
 2.00000+00 0.00000+00 8.60000-02 8.00000-03 0.00000+00 0.00000+00 230 8457  159
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  160
 9.37950+06 5.00000+02          0          0         12          0 230 8457  161
 2.00000+00 0.00000+00 2.02000-02 2.50000-03 0.00000+00 0.00000+00 230 8457  162
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  163
 9.47740+06 9.00000+02          0          0         12          0 230 8457  164
 2.00000+00 0.00000+00 5.50000-02 7.00000-03 0.00000+00 0.00000+00 230 8457  165
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  166
 9.79380+06 1.00000+03          0          0         12          0 230 8457  167
 2.00000+00 0.00000+00 1.30000-02 3.00000-03 0.00000+00 0.00000+00 230 8457  168
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 230 8457  169
 0.00000+00 2.00000+00          0          0          6         26 230 8457  170
 1.00000-02 0.00000+00 4.58697+06 4.27770+04 0.00000+00 0.00000+00 230 8457  171
 1.23822+06 4.00903+03          0          0          6          0 230 8457  172
 2.00000+00 1.00000+00 2.30000-05 1.20000-05 2.40000-06 1.20000-06 230 8457  173
 1.43181+06 4.00903+03          0          0          6          0 230 8457  174
 2.00000+00 1.00000+00 1.60000-04 5.00000-05 8.00000-05 3.00000-05 230 8457  175
 1.60582+06 4.00903+03          0          0          6          0 230 8457  176
 2.00000+00 1.00000+00 1.90000-04 6.00000-05 1.50000-04 5.00000-05 230 8457  177
 1.61691+06 4.00903+03          0          0          6          0 230 8457  178
 2.00000+00 2.00000+00 2.70000-05 7.00000-06 2.10000-05 6.00000-06 230 8457  179
 1.75813+06 4.00903+03          0          0          6          0 230 8457  180
 2.00000+00 1.00000+00 3.80000-04 9.00000-05 3.40000-04 8.00000-05 230 8457  181
 1.78072+06 4.00903+03          0          0          6          0 230 8457  182
 2.00000+00 1.00000+00 7.10000-05 7.00000-06 6.40000-05 6.00000-06 230 8457  183
 1.89066+06 4.00903+03          0          0          6          0 230 8457  184
 2.00000+00 1.00000+00 1.20000-03 3.00000-04 1.10000-03 3.00000-04 230 8457  185
 2.04138+06 4.00903+03          0          0          6          0 230 8457  186
 2.00000+00 1.00000+00 7.10000-04 1.80000-04 6.80000-04 1.70000-04 230 8457  187
 2.25946+06 4.00903+03          0          0          6          0 230 8457  188
 2.00000+00 1.00000+00 8.90000-05 2.20000-05 8.70000-05 2.10000-05 230 8457  189
 2.39968+06 4.46968+03          0          0          6          0 230 8457  190
 2.00000+00 1.00000+00 4.50000-04 4.50000-04 8.80000-04 0.00000+00 230 8457  191
 2.67393+06 4.02891+03          0          0          6          0 230 8457  192
 2.00000+00 1.00000+00 2.40000-04 6.00000-05 2.40000-04 6.00000-05 230 8457  193
 2.81515+06 4.01774+03          0          0          6          0 230 8457  194
 2.00000+00 1.00000+00 7.70000-05 2.00000-05 7.60000-05 2.00000-05 230 8457  195
 3.66199+06 6.39960+03          0          0          6          0 230 8457  196
 2.00000+00 1.00000+00 3.00000-01 1.00000-02 2.99000-01 1.00000-02 230 8457  197
 4.12072+06 4.00280+03          0          0          6          0 230 8457  198
 2.00000+00 1.00000+00 2.90000-02 4.00000-03 2.90000-02 4.00000-03 230 8457  199
 4.53356+06 4.00025+03          0          0          6          0 230 8457  200
 2.00000+00 1.00000+00 5.30000-02 7.00000-03 5.30000-02 7.00000-03 230 8457  201
 4.84893+06 4.26965+03          0          0          6          0 230 8457  202
 2.00000+00 1.00000+00 6.50000-02 7.00000-03 6.50000-02 7.00000-03 230 8457  203
 4.94808+06 4.04253+03          0          0          6          0 230 8457  204
 2.00000+00 1.00000+00 5.90000-01 3.00000-02 5.90000-01 3.00000-02 230 8457  205
 5.01314+06 4.02891+03          0          0          6          0 230 8457  206
 2.00000+00 1.00000+00 1.13000+01 4.00000-01 1.13000+01 4.00000-01 230 8457  207
 5.73994+06 4.04253+03          0          0          6          0 230 8457  208
 2.00000+00 1.00000+00 3.64000+00 1.10000-01 3.64000+00 1.10000-01 230 8457  209
 6.06926+06 4.04253+03          0          0          6          0 230 8457  210
 2.00000+00 1.00000+00 5.37000-01 1.10000-02 5.37000-01 1.10000-02 230 8457  211
 6.39508+06 4.01774+03          0          0          6          0 230 8457  212
 2.00000+00 1.00000+00 2.84000+00 2.00000-01 2.84000+00 2.00000-01 230 8457  213
 6.52961+06 4.01774+03          0          0          6          0 230 8457  214
 2.00000+00 1.00000+00 2.44000+00 9.00000-02 2.44000+00 9.00000-02 230 8457  215
 6.91200+06 3.99905+03          0          0          6          0 230 8457  216
 2.00000+00 1.00000+00 1.90000-01 6.00000-02 1.90000-01 6.00000-02 230 8457  217
 8.05107+06 4.00280+03          0          0          6          0 230 8457  218
 2.00000+00 1.00000+00 7.60000+00 4.00000-01 7.60000+00 4.00000-01 230 8457  219
 9.70886+06 4.00280+03          0          0          6          0 230 8457  220
 2.00000+00 1.00000+00 1.29000+00 1.80000-01 1.29000+00 1.80000-01 230 8457  221
 1.25461+07 3.99881+03          0          0          6          0 230 8457  222
 2.00000+00 1.00000+00 6.91000+01 7.00000-01 6.91000+01 7.00000-01 230 8457  223
 0.00000+00 9.00000+00          0          0          6          1 230 8457  224
 1.00000-02 0.00000+00 1.02176+06 3.64783+04 0.00000+00 0.00000+00 230 8457  225
 5.10999+05 1.50000-01          0          0          6          0 230 8457  226
 2.00000+00 0.00000+00 1.99953+02 7.13863+00 0.00000+00 0.00000+00 230 8457  227
                                                                   230 8  099999
                                                                   230 0  0    0
                                                                     0 0  0    0
 1.502900+4 2.873280+1         -1          0          2          1 231 1451    1
 0.000000+0 1.000000+0          0          0          0          6 231 1451    2
 0.000000+0 0.000000+0          0          0          4        311 231 1451    3
 0.000000+0 0.000000+0          0          0         18          2 231 1451    4
 15-P - 29 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  231 1451    5
                      DIST-NOV07                       261107      231 1451    6
----JEFF-311          MATERIAL  231                                231 1451    7
-----RADIOACTIVE DECAY DATA                                        231 1451    8
------ENDF-6 FORMAT                                                231 1451    9
****************************************************************** 231 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 231 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 231 1451   12
**             Original data taken from:  NUBASE                ** 231 1451   13
****************************************************************** 231 1451   14
****************************************************************** 231 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 231 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      231 1451   17
                                                                   231 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           231 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        231 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               231 1451   21
****************************************************************** 231 1451   22
                                1        451         24          0 231 1451   23
                                8        457          5          0 231 1451   24
 0.000000+0 0.000000+0          0          0          0          0 231 1  099999
                                                                   231 0  0    0
 1.50290+04 2.87328+01          0          0          0          0 231 8457    1
 4.14200+00 1.50000-02          0          0          6          0 231 8457    2
 1.64748+06 0.00000+00 1.64748+06 0.00000+00 0.00000+00 0.00000+00 231 8457    3
 5.00000-01 1.00000+00          0          0          6          1 231 8457    4
 2.00000+00 0.00000+00 4.94245+06 0.00000+00 1.00000+00 0.00000+00 231 8457    5
                                                                   231 8  099999
                                                                   231 0  0    0
                                                                     0 0  0    0
 1.503000+4 2.972080+1         -1          0          2          1 232 1451    1
 0.000000+0 1.000000+0          0          0          0          6 232 1451    2
 0.000000+0 0.000000+0          0          0          4        311 232 1451    3
 0.000000+0 0.000000+0          0          0         47          2 232 1451    4
 15-P - 30 ENSDF      EVAL-MAR01 CONVERSION OF ENSDF               232 1451    5
 /ENSDF/              DIST-NOV07                       261107      232 1451    6
----JEFF-311          MATERIAL  232                                232 1451    7
-----RADIOACTIVE DECAY DATA                                        232 1451    8
------ENDF-6 FORMAT                                                232 1451    9
****************************************************************** 232 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 232 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 232 1451   12
**             Original data taken from:  ENSDF                 ** 232 1451   13
****************************************************************** 232 1451   14
****************************************************************** 232 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 232 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 232 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 232 1451   18
****************************************************************** 232 1451   19
30P   DECAY 2.498 M   4                     I(min) = 0.0E+00 %     232 1451   20
         Ex = 0           keV                     1 decay mode(s)  232 1451   21
                                                                   232 1451   22
30P B+ DECAY                Q =  4232.3000 keV       0.4000        232 1451   23
         Branching                100.0000 %         0.0000        232 1451   24
                         Br*Q =  4232.3000 keV       0.4000        232 1451   25
                                              0 isomeric state(s)  232 1451   26
                                                                   232 1451   27
Individual beta+ transitions                                       232 1451   28
Final level    end point    shape    av.energy        intensity    232 1451   29
 2235.320    974.834   0.400  0    399.800   0.700    0.052 0.003  232 1451   30
    0.000   3209.815   0.400  0   1438.000   0.800   99.803 0.004  232 1451   31
                                                                   232 1451   32
         Mean alpha    energy       0.0000 keV       0.0000        232 1451   33
         Mean beta     energy    1435.3750 keV       0.8006        232 1451   34
         Mean conv. e- energy       0.0003 keV       0.0001        232 1451   35
         Mean Auger e- energy       0.0001 keV       0.0000        232 1451   36
         Mean gamma    energy    1022.1523 keV                     232 1451   37
         Mean X        energy       0.0000 keV       0.0000        232 1451   38
         Mean recoil   energy       0.4857 keV       0.0001        232 1451   39
         Mean neutrino energy    1774.4880 keV       0.4101        232 1451   40
         Mean neutron  energy       0.0000 keV       0.0000        232 1451   41
         Total         energy    4232.5015 keV       0.9400        232 1451   42
         Q effective             4232.3000 keV       0.4000        232 1451   43
         diff. mode                 0.2015 keV       0.0048 %      232 1451   44
                                                                   232 1451   45
         Mean e- bind. energy       0.0001 keV                     232 1451   46
         diff. atomic               0.0000 keV     -12.7567 %      232 1451   47
         diff. nuclear              0.2015 keV       0.0048 %      232 1451   48
                                                                   232 1451   49
         B+ fraction               99.8550 %         0.0050        232 1451   50
                                                                   232 1451   51
                                1        451         53          0 232 1451   52
                                8        457         49          0 232 1451   53
 0.000000+0 0.000000+0          0          0          0          0 232 1  099999
                                                                   232 0  0    0
 1.50300+04 2.97208+01          0          0          0          4 232 8457    1
 1.49880+02 2.40000-01          0          0          6          0 232 8457    2
 1.43538+06 8.00583+02 1.02215+06 2.73116+02 0.00000+00 0.00000+00 232 8457    3
 1.00000+00 1.00000+00          0          0          6          1 232 8457    4
 2.00000+00 0.00000+00 4.23230+06 4.00000+02 1.00000+00 0.00000+00 232 8457    5
 0.00000+00 0.00000+00          0          0          6          6 232 8457    6
 1.00000-02 0.00000+00 1.63611+03 2.68293+02 0.00000+00 0.00000+00 232 8457    7
 1.26321+06 5.00000+01          0          0         12          0 232 8457    8
 2.00000+00 0.00000+00 8.10000-04 8.00000-05 0.00000+00 0.00000+00 232 8457    9
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 232 8457   10
 1.53416+06 5.00000+01          0          0         12          0 232 8457   11
 2.00000+00 0.00000+00 1.00000-04 2.00000-05 0.00000+00 0.00000+00 232 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 232 8457   13
 1.55236+06 6.00000+01          0          0         12          0 232 8457   14
 2.00000+00 0.00000+00 3.40000-03 3.00000-04 0.00000+00 0.00000+00 232 8457   15
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 232 8457   16
 2.23523+06 2.00000+01          0          0         12          0 232 8457   17
 2.00000+00 0.00000+00 6.90000-02 1.20000-02 0.00000+00 0.00000+00 232 8457   18
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 232 8457   19
 3.49833+06 4.00000+01          0          0         12          0 232 8457   20
 2.00000+00 0.00000+00 7.50000-04 1.00000-04 0.00000+00 0.00000+00 232 8457   21
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 232 8457   22
 3.76925+06 4.00000+01          0          0         12          0 232 8457   23
 2.00000+00 0.00000+00 8.00000-05 1.00000-05 0.00000+00 0.00000+00 232 8457   24
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 232 8457   25
 0.00000+00 2.00000+00          0          0          6          5 232 8457   26
 1.00000-02 0.00000+00 1.43538+06 8.00583+02 0.00000+00 0.00000+00 232 8457   27
 4.44590+05 4.03113+02          0          0          6          0 232 8457   28
 2.00000+00 1.00000+00 3.40000-03 3.00000-04 0.00000+00 0.00000+00 232 8457   29
 4.62780+05 4.01995+02          0          0          6          0 232 8457   30
 2.00000+00 1.00000+00 1.80000-04 4.00000-05 0.00000+00 0.00000+00 232 8457   31
 7.33750+05 4.01995+02          0          0          6          0 232 8457   32
 2.00000+00 1.00000+00 1.56000-03 1.50000-04 0.00000+00 0.00000+00 232 8457   33
 1.99668+06 4.00439+02          0          0          6          0 232 8457   34
 2.00000+00 1.00000+00 5.50000-02 3.00000-03 5.20000-02 3.00000-03 232 8457   35
 4.23166+06 3.99939+02          0          0          6          0 232 8457   36
 2.00000+00 1.00000+00 9.99400+01 3.00000-03 9.98030+01 4.00000-03 232 8457   37
 0.00000+00 8.00000+00          0          0          6          2 232 8457   38
 1.00000-02 0.00000+00 4.51645-01 7.58950-02 0.00000+00 0.00000+00 232 8457   39
 1.61000+03 0.00000+00          0          0          6          0 232 8457   40
 2.00000+00 0.00000+00 6.89066-03 3.26924-04 0.00000+00 0.00000+00 232 8457   41
 3.78561+06 5.00016+01          0          0          6          0 232 8457   42
 2.00000+00 0.00000+00 9.00000-06 2.00000-06 0.00000+00 0.00000+00 232 8457   43
 0.00000+00 9.00000+00          0          0          6          2 232 8457   44
 1.00000-02 0.00000+00 1.02052+06 9.14108+01 0.00000+00 0.00000+00 232 8457   45
 1.73998+03 3.00000-02          0          0          6          0 232 8457   46
 2.00000+00 0.00000+00 3.39833-04 5.99812-05 0.00000+00 0.00000+00 232 8457   47
 5.10999+05 1.50000-01          0          0          6          0 232 8457   48
 2.00000+00 0.00000+00 1.99710+02 1.78885-02 0.00000+00 0.00000+00 232 8457   49
                                                                   232 8  099999
                                                                   232 0  0    0
                                                                     0 0  0    0
 1.503100+4 3.070770+1         -1          0          2          1 233 1451    1
 0.000000+0 0.000000+0          0          0          0          6 233 1451    2
 0.000000+0 0.000000+0          0          0          4        311 233 1451    3
 0.000000+0 0.000000+0          0          0         22          2 233 1451    4
 15-P - 31 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  233 1451    5
                      DIST-NOV07                       261107      233 1451    6
----JEFF-311          MATERIAL  233                                233 1451    7
-----RADIOACTIVE DECAY DATA                                        233 1451    8
------ENDF-6 FORMAT                                                233 1451    9
****************************************************************** 233 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 233 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 233 1451   12
**             Original data taken from:  NUBASE                ** 233 1451   13
****************************************************************** 233 1451   14
****************************************************************** 233 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 233 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      233 1451   17
                                                                   233 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           233 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        233 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               233 1451   21
****************************************************************** 233 1451   22
STABLE NUCLEUS                                                     233 1451   23
       SPIN          0.5                                           233 1451   24
       PARITY        1.0                                           233 1451   25
NATURAL ABUNDANCE  100.          %                                 233 1451   26
                                1        451         28          0 233 1451   27
                                8        457          5          0 233 1451   28
 0.000000+0 0.000000+0          0          0          0          0 233 1  099999
                                                                   233 0  0    0
 1.50310+04 3.07077+01          0          0          1          0 233 8457    1
 0.00000+00 0.00000+00          0          0          6          0 233 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 233 8457    3
 5.00000-01 1.00000+00          0          0          6          0 233 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 233 8457    5
                                                                   233 8  099999
                                                                   233 0  0    0
                                                                     0 0  0    0
 1.503200+4 3.169920+1         -1          0          2          1 234 1451    1
 0.000000+0 1.000000+0          0          0          0          6 234 1451    2
 0.000000+0 0.000000+0          0          0          4        311 234 1451    3
 0.000000+0 0.000000+0          0          0         35          2 234 1451    4
 15-P - 32 HAR+WIN    EVAL-NOV82 A.L. NICHOLS                      234 1451    5
                      DIST-NOV07                       261107      234 1451    6
----JEFF-311          MATERIAL  234                                234 1451    7
-----RADIOACTIVE DECAY DATA                                        234 1451    8
------ENDF-6 FORMAT                                                234 1451    9
****************************************************************** 234 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 234 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 234 1451   12
**             Original data taken from:  UKPADD67              ** 234 1451   13
****************************************************************** 234 1451   14
      P.M.ENDT, C.VAN DER LEUN     NUCL PHYS   A310(1978)1         234 1451   15
      D.W.PERNAA         INT J APPL RAD ISOTOPES  20(1969)613      234 1451   16
      F.LAGOUTINE ET AL  INT J APPL RAD ISOTOPES  20(1969)868      234 1451   17
      R.PRASAD BABU ET AL          PHYS REV    C13(1976)1267       234 1451   18
      M.S.POWAR, M.SINGH           J PHYS G, NUCL PHYS 2(1976)43   234 1451   19
                                                                   234 1451   20
          THEORETICAL CALCULATIONS AND MEASUREMENTS HAVE BEEN      234 1451   21
      MADE OF INTERNAL PAIR FORMATION:                             234 1451   22
      J.S.GREENBERG, M.DEUTSCH     PHYS REV   102(1956)415         234 1451   23
      K.HUANG                      PHYS REV   102(1956)422         234 1451   24
      A POSITRON-ELECTRON RATIO OF 7.5(2.0)E-10 HAS BEEN ASSIGNED. 234 1451   25
                                                                   234 1451   26
                                                                   234 1451   27
      MEAN BETA- ENERGIES:-                                        234 1451   28
   END POINT(MEV)= 1.7104  SHAPE= 0  MEAN= 0.6946  INT= 1.0000     234 1451   29
                                                                   234 1451   30
      MEAN BETA- ENERGY              =    692.9170  KEV            234 1451   31
      BETA- + NEUTRINO ENERGY        =   1710.4000  KEV            234 1451   32
      INTERNAL BREMSSTRAHLUNG ENERGY =      1.7104  KEV            234 1451   33
      EFFECTIVE Q VALUE              =   1710.4000  KEV            234 1451   34
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0351                 234 1451   35
      CALCULATED Q VALUE             =   1710.4000  KEV            234 1451   36
      % DEVIATION                    =      0.0000                 234 1451   37
                                                                   234 1451   38
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).          234 1451   39
                                1        451         41          1 234 1451   40
                                8        457          9          1 234 1451   41
 0.000000+0 0.000000+0          0          0          0          0 234 1  099999
                                                                   234 0  0    0
1.50320E+043.16992E+01          0          0          0          1 234 8457    1
1.23293E+063.45600E+03          0          0          6          0 234 8457    2
6.92917E+056.95055E+031.71040E+031.71040E+020.00000E+000.00000E+00 234 8457    3
1.00000E+00 1.0000E+00          0          0          6          1 234 8457    4
1.00000E+000.00000E+001.71040E+066.00000E+021.00000E+000.00000E+00 234 8457    5
0.00000E+001.00000E+00          0          0          6          1 234 8457    6
1.00000E+000.00000E+006.92917E+056.95055E+030.00000E+000.00000E+00 234 8457    7
1.71040E+066.00000E+02          0          0          6          0 234 8457    8
1.00000E+001.00000E+001.00000E+001.00000E-020.00000E+000.00000E+00 234 8457    9
                                                                   234 8  099999
                                                                   234 0  0    0
                                                                     0 0  0    0
 1.503300+4 3.268850+1         -1          0          2          1 235 1451    1
 0.000000+0 1.000000+0          0          0          0          6 235 1451    2
 0.000000+0 0.000000+0          0          0          4        311 235 1451    3
 0.000000+0 0.000000+0          0          0         47          2 235 1451    4
 15-P - 33 SAC        EVAL-FEB03 V.CHISTE, M.M.BE                  235 1451    5
 /DDEP/               DIST-NOV07                       261107      235 1451    6
----JEFF-311          MATERIAL  235                                235 1451    7
-----RADIOACTIVE DECAY DATA                                        235 1451    8
------ENDF-6 FORMAT                                                235 1451    9
****************************************************************** 235 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 235 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 235 1451   12
**             Original data taken from:  LNHB                  ** 235 1451   13
****************************************************************** 235 1451   14
****************************************************************** 235 1451   15
*Data from the Laboratoire National Henri Becquerel, BNM-CEA/LNHB* 235 1451   16
*              http://www.nucleide.org/NucData.htm               * 235 1451   17
****************************************************************** 235 1451   18
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 235 1451   19
*     (the CEA-Bruyeres version of the RADLST program).          * 235 1451   20
* (1) 0. Bersillon and J. Blachot, to be published.              * 235 1451   21
****************************************************************** 235 1451   22
DECAY 25.383 D  40                    I(min) = 0.0E+00 %           235 1451   23
         Ex = 0.0         keV                     1 decay mode(s)  235 1451   24
                                                                   235 1451   25
 33P  B- DECAY              Q =   248.5000 keV       1.1000        235 1451   26
         Branching                100.0000 %         0.0000        235 1451   27
                         Br*Q =   248.5000 keV       1.1000        235 1451   28
                                              0 isomeric state(s)  235 1451   29
                                                                   235 1451   30
Individual beta- transitions                                       235 1451   31
Final level    end point    shape    av.energy        intensity    235 1451   32
    0.000    248.498   1.100  0     76.400   0.500  100.000 0.000  235 1451   33
                                                                   235 1451   34
         Mean alpha    energy       0.0000 keV       0.0000        235 1451   35
         Mean beta     energy      76.4000 keV       0.5000        235 1451   36
         Mean conv. e- energy       0.0000 keV       0.0000        235 1451   37
         Mean Auger e- energy       0.0000 keV       0.0000        235 1451   38
         Mean gamma    energy       0.0000 keV                     235 1451   39
         Mean X        energy       0.0000 keV       0.0000        235 1451   40
         Mean recoil   energy       0.0020 keV       0.0000        235 1451   41
         Mean neutrino energy     172.0980 keV       0.5000        235 1451   42
         Mean neutron  energy       0.0000 keV       0.0000        235 1451   43
         Total         energy     248.5000 keV       0.7071        235 1451   44
         Q effective              248.5000 keV       1.1000        235 1451   45
         diff. mode                 0.0000 keV       0.0000 %      235 1451   46
                                                                   235 1451   47
         Mean e- bind. energy       0.0000 keV                     235 1451   48
         diff. atomic               0.0000 keV       0.0000 %      235 1451   49
         diff. nuclear              0.0000 keV       0.0000 %      235 1451   50
                                                                   235 1451   51
                                1        451         53          0 235 1451   52
                                8        457          9          0 235 1451   53
 0.000000+0 0.000000+0          0          0          0          0 235 1  099999
                                                                   235 0  0    0
 1.50330+04 3.26885+01          0          0          0          1 235 8457    1
 2.19309+06 3.45600+03          0          0          6          0 235 8457    2
 7.64000+04 5.00000+02 0.00000+00 0.00000+00 0.00000+00 0.00000+00 235 8457    3
 5.00000-01 1.00000+00          0          0          6          1 235 8457    4
 1.00000+00 0.00000+00 2.48500+05 1.10000+03 1.00000+00 0.00000+00 235 8457    5
 0.00000+00 1.00000+00          0          0          6          1 235 8457    6
 1.00000-02 0.00000+00 7.64000+04 5.00000+02 0.00000+00 0.00000+00 235 8457    7
 2.48498+05 1.09999+03          0          0          6          0 235 8457    8
 1.00000+00 1.00000+00 1.00000+02 0.00000+00 0.00000+00 0.00000+00 235 8457    9
                                                                   235 8  099999
                                                                   235 0  0    0
                                                                     0 0  0    0
 1.503400+4 3.368180+1         -1          0          2          1 236 1451    1
 0.000000+0 1.000000+0          0          0          0          6 236 1451    2
 0.000000+0 0.000000+0          0          0          4        311 236 1451    3
 0.000000+0 0.000000+0          0          0         40          2 236 1451    4
 15-P - 34 HAR+WIN    EVAL-NOV82 A.L. NICHOLS                      236 1451    5
                      DIST-NOV07 REV1-DEC94            261107      236 1451    6
----JEFF-311          MATERIAL  236         REVISION 1             236 1451    7
-----RADIOACTIVE DECAY DATA                                        236 1451    8
------ENDF-6 FORMAT                                                236 1451    9
****************************************************************** 236 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 236 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 236 1451   12
**             Original data taken from:  UKPADD67              ** 236 1451   13
****************************************************************** 236 1451   14
      P.M.ENDT, C.VAN DER LEUN     NUCL PHYS   A310(1978)1         236 1451   15
      T.E.WARD, P.K.KURODA      J INORG NUCL CHEM  33(1971)609     236 1451   16
      D.R.GOOSMAN ET AL            PHYS REV      C8(1973)1324      236 1451   17
                                                                   236 1451   18
          THE RELATIVE GAMMA INTENSITY DATA OF GOOSMAN ET AL HAVE  236 1451   19
      BEEN USED TO DERIVE A DECAY SCHEME.  ABSOLUTE INTENSITY DATA 236 1451   20
      HAVE BEEN CALCULATED ASSUMING A BETA BRANCH TO THE 34-S      236 1451   21
      GROUND STATE OF APPROXIMATELY 85% BY WARD AND KURODA.        236 1451   22
                                                                   236 1451   23
      RE-EVAL                                                      236 1451   24
      P.M.ENDT                     NUCL PHYS   A521(1990)1         236 1451   25
                                                                   236 1451   26
                                                                   236 1451   27
      MEAN BETA- ENERGIES:-                                        236 1451   28
   END POINT(MEV)= 1.2595  SHAPE= 0  MEAN= 0.4899  INT= 0.0033     236 1451   29
   END POINT(MEV)= 1.2996  SHAPE= 0  MEAN= 0.5078  INT= 0.0011     236 1451   30
   END POINT(MEV)= 1.4579  SHAPE= 0  MEAN= 0.5791  INT= 0.0005     236 1451   31
   END POINT(MEV)= 3.2467  SHAPE= 0  MEAN= 1.4226  INT= 0.1490     236 1451   32
   END POINT(MEV)= 5.3743  SHAPE= 0  MEAN= 2.4582  INT= 0.8460     236 1451   33
                                                                   236 1451   34
      MEAN GAMMA ENERGY              =    337.9586  KEV            236 1451   35
      MEAN BETA- ENERGY              =   2284.5544  KEV            236 1451   36
      BETA- + NEUTRINO ENERGY        =   5036.6729  KEV            236 1451   37
      INTERNAL BREMSSTRAHLUNG ENERGY =      9.5210  KEV            236 1451   38
      EFFECTIVE Q VALUE              =   5374.2998  KEV            236 1451   39
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0223                 236 1451   40
      CALCULATED Q VALUE             =   5374.6309  KEV            236 1451   41
      % DEVIATION                    =     -0.0062                 236 1451   42
                                                                   236 1451   43
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).          236 1451   44
                                1        451         46          1 236 1451   45
                                8        457         37          1 236 1451   46
 0.000000+0 0.000000+0          0          0          0          0 236 1  099999
                                                                   236 0  0    0
1.50340E+043.36818E+01          0          0          0          2 236 8457    1
1.24000E+011.00000E-01          0          0          6          0 236 8457    2
2.28455E+068.60071E+033.47480E+059.06514E+030.00000E+000.00000E+00 236 8457    3
1.00000E+00 1.0000E+00          0          0          6          1 236 8457    4
1.00000E+000.00000E+005.37430E+061.20000E+031.00000E+000.00000E+00 236 8457    5
0.00000E+000.00000E+00          0          0          6          6 236 8457    6
1.52000E-014.00000E-033.37959E+059.01500E+030.00000E+000.00000E+00 236 8457    7
1.78885E+063.00000E+01          0          0         12          0 236 8457    8
1.00000E+000.00000E+003.00000E-031.00000E-030.00000E+000.00000E+00 236 8457    9
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 236 8457   10
1.94711E+062.00000E+01          0          0         12          0 236 8457   11
1.00000E+000.00000E+004.00000E-036.00000E-040.00000E+000.00000E+00 236 8457   12
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 236 8457   13
1.98725E+063.00000E+01          0          0         12          0 236 8457   14
1.00000E+000.00000E+001.00000E-022.00000E-030.00000E+000.00000E+00 236 8457   15
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 236 8457   16
2.12756E+061.00000E+01          0          0         12          0 236 8457   17
1.00000E+000.00000E+001.00000E+000.00000E+000.00000E+000.00000E+00 236 8457   18
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 236 8457   19
4.07467E+061.00000E+01          0          0         12          0 236 8457   20
1.00000E+000.00000E+003.30000E-036.00000E-040.00000E+000.00000E+00 236 8457   21
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 236 8457   22
4.11481E+062.00000E+01          0          0         12          0 236 8457   23
1.00000E+000.00000E+001.20000E-022.00000E-030.00000E+000.00000E+00 236 8457   24
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 236 8457   25
0.00000E+001.00000E+00          0          0          6          5 236 8457   26
1.00000E+000.00000E+002.28455E+068.60071E+030.00000E+000.00000E+00 236 8457   27
1.25950E+061.20000E+03          0          0          6          0 236 8457   28
1.00000E+001.00000E+003.30000E-036.00000E-040.00000E+000.00000E+00 236 8457   29
1.29960E+061.20000E+03          0          0          6          0 236 8457   30
1.00000E+001.00000E+001.10000E-032.00000E-040.00000E+000.00000E+00 236 8457   31
1.45790E+061.20000E+03          0          0          6          0 236 8457   32
1.00000E+001.00000E+004.60000E-041.50000E-040.00000E+000.00000E+00 236 8457   33
3.24670E+061.20000E+03          0          0          6          0 236 8457   34
1.00000E+001.00000E+001.49000E-013.00000E-030.00000E+000.00000E+00 236 8457   35
5.37430E+061.20000E+03          0          0          6          0 236 8457   36
1.00000E+001.00000E+008.46000E-013.00000E-030.00000E+000.00000E+00 236 8457   37
                                                                   236 8  099999
                                                                   236 0  0    0
                                                                     0 0  0    0
 1.503500+4 3.467290+1         -1          0          2          1 237 1451    1
 0.000000+0 1.000000+0          0          0          0          6 237 1451    2
 0.000000+0 0.000000+0          0          0          4        311 237 1451    3
 0.000000+0 0.000000+0          0          0         18          2 237 1451    4
 15-P - 35 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  237 1451    5
                      DIST-NOV07                       261107      237 1451    6
----JEFF-311          MATERIAL  237                                237 1451    7
-----RADIOACTIVE DECAY DATA                                        237 1451    8
------ENDF-6 FORMAT                                                237 1451    9
****************************************************************** 237 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 237 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 237 1451   12
**             Original data taken from:  NUBASE                ** 237 1451   13
****************************************************************** 237 1451   14
****************************************************************** 237 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 237 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      237 1451   17
                                                                   237 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           237 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        237 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               237 1451   21
****************************************************************** 237 1451   22
                                1        451         24          0 237 1451   23
                                8        457          5          0 237 1451   24
 0.000000+0 0.000000+0          0          0          0          0 237 1  099999
                                                                   237 0  0    0
 1.50350+04 3.46729+01          0          0          0          0 237 8457    1
 4.73000+01 7.00000-01          0          0          6          0 237 8457    2
 1.32955+06 0.00000+00 1.32955+06 0.00000+00 0.00000+00 0.00000+00 237 8457    3
 5.00000-01 1.00000+00          0          0          6          1 237 8457    4
 1.00000+00 0.00000+00 3.98866+06 0.00000+00 1.00000+00 0.00000+00 237 8457    5
                                                                   237 8  099999
                                                                   237 0  0    0
                                                                     0 0  0    0
 1.503600+4 3.566920+1         -1          0          2          1 238 1451    1
 0.000000+0 1.000000+0          0          0          0          6 238 1451    2
 0.000000+0 0.000000+0          0          0          4        311 238 1451    3
 0.000000+0 0.000000+0          0          0         18          2 238 1451    4
 15-P - 36 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  238 1451    5
                      DIST-NOV07                       261107      238 1451    6
----JEFF-311          MATERIAL  238                                238 1451    7
-----RADIOACTIVE DECAY DATA                                        238 1451    8
------ENDF-6 FORMAT                                                238 1451    9
****************************************************************** 238 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 238 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 238 1451   12
**             Original data taken from:  NUBASE                ** 238 1451   13
****************************************************************** 238 1451   14
****************************************************************** 238 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 238 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      238 1451   17
                                                                   238 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           238 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        238 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               238 1451   21
****************************************************************** 238 1451   22
                                1        451         24          0 238 1451   23
                                8        457          5          0 238 1451   24
 0.000000+0 0.000000+0          0          0          0          0 238 1  099999
                                                                   238 0  0    0
 1.50360+04 3.56692+01          0          0          0          0 238 8457    1
 5.60000+00 3.00000-01          0          0          6          0 238 8457    2
 3.47102+06 0.00000+00 3.47102+06 0.00000+00 0.00000+00 0.00000+00 238 8457    3
 4.00000+00-1.00000+00          0          0          6          1 238 8457    4
 1.00000+00 0.00000+00 1.04131+07 0.00000+00 1.00000+00 0.00000+00 238 8457    5
                                                                   238 8  099999
                                                                   238 0  0    0
                                                                     0 0  0    0
 1.503700+4 3.666190+1         -1          0          2          1 239 1451    1
 0.000000+0 1.000000+0          0          0          0          6 239 1451    2
 0.000000+0 0.000000+0          0          0          4        311 239 1451    3
 0.000000+0 0.000000+0          0          0         18          2 239 1451    4
 15-P - 37 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  239 1451    5
                      DIST-NOV07                       261107      239 1451    6
----JEFF-311          MATERIAL  239                                239 1451    7
-----RADIOACTIVE DECAY DATA                                        239 1451    8
------ENDF-6 FORMAT                                                239 1451    9
****************************************************************** 239 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 239 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 239 1451   12
**             Original data taken from:  NUBASE                ** 239 1451   13
****************************************************************** 239 1451   14
****************************************************************** 239 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 239 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      239 1451   17
                                                                   239 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           239 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        239 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               239 1451   21
****************************************************************** 239 1451   22
                                1        451         24          0 239 1451   23
                                8        457          5          0 239 1451   24
 0.000000+0 0.000000+0          0          0          0          0 239 1  099999
                                                                   239 0  0    0
 1.50370+04 3.66619+01          0          0          0          0 239 8457    1
 2.31000+00 1.30000-01          0          0          6          0 239 8457    2
 2.63545+06 0.00000+00 2.63545+06 0.00000+00 0.00000+00 0.00000+00 239 8457    3
 5.00000-01 1.00000+00          0          0          6          1 239 8457    4
 1.00000+00 0.00000+00 7.90636+06 0.00000+00 1.00000+00 0.00000+00 239 8457    5
                                                                   239 8  099999
                                                                   239 0  0    0
                                                                     0 0  0    0
 1.503800+4 3.765780+1         -1          0          2          1 240 1451    1
 0.000000+0 1.000000+0          0          0          0          6 240 1451    2
 0.000000+0 0.000000+0          0          0          4        311 240 1451    3
 0.000000+0 0.000000+0          0          0         47          2 240 1451    4
 15-P - 38 ENSDF      EVAL-MAR01 CONVERSION OF ENSDF               240 1451    5
 /ENSDF/              DIST-NOV07                       261107      240 1451    6
----JEFF-311          MATERIAL  240                                240 1451    7
-----RADIOACTIVE DECAY DATA                                        240 1451    8
------ENDF-6 FORMAT                                                240 1451    9
****************************************************************** 240 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 240 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 240 1451   12
**             Original data taken from:  ENSDF                 ** 240 1451   13
****************************************************************** 240 1451   14
****************************************************************** 240 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 240 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 240 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 240 1451   18
****************************************************************** 240 1451   19
38P   DECAY 0.64 S    14                    I(min) = 0.0E+00 %     240 1451   20
         Ex = 0           keV                     1 decay mode(s)  240 1451   21
                                                                   240 1451   22
38P B- DECAY                Q = 12390.0000 keV     140.0000        240 1451   23
         Branching                100.0000 %         0.0000        240 1451   24
                         Br*Q = 12390.0000 keV     140.0000        240 1451   25
                                              0 isomeric state(s)  240 1451   26
                                                                   240 1451   27
Individual beta- transitions                                       240 1451   28
Final level    end point    shape    av.energy        intensity    240 1451   29
 6005.900   6381.917 139.956  0   2900.000   0.000   10.000 3.000  240 1451   30
 4990.500   7396.969 139.956  0   3400.000   0.000   11.000 3.000  240 1451   31
 3516.400   8870.565 139.954  0   4100.000   0.000   36.000 6.000  240 1451   32
 1292.000  11094.204 139.952  0   5000.000   0.000   43.000 8.000  240 1451   33
                                                                   240 1451   34
         Mean alpha    energy       0.0000 keV       0.0000        240 1451   35
         Mean beta     energy    4290.0000 keV     488.3534        240 1451   36
         Mean conv. e- energy       0.0000 keV       0.0000        240 1451   37
         Mean Auger e- energy       0.0000 keV       0.0000        240 1451   38
         Mean gamma    energy    2777.8982 keV                     240 1451   39
         Mean X        energy       0.0000 keV       0.0000        240 1451   40
         Mean recoil   energy       3.2214 keV       0.3690        240 1451   41
         Mean neutrino energy    5125.7696 keV     587.2913        240 1451   42
         Mean neutron  energy       0.0000 keV       0.0000        240 1451   43
         Total         energy   12196.9910 keV     801.8915        240 1451   44
         Q effective            12390.0000 keV     140.0000        240 1451   45
         diff. mode              -193.0090 keV      -1.5578 %      240 1451   46
                                                                   240 1451   47
         Mean e- bind. energy       0.0000 keV                     240 1451   48
         diff. atomic               0.0000 keV       0.0000 %      240 1451   49
         diff. nuclear           -193.0090 keV      -1.5578 %      240 1451   50
                                                                   240 1451   51
                                1        451         53          0 240 1451   52
                                8        457         32          0 240 1451   53
 0.000000+0 0.000000+0          0          0          0          0 240 1  099999
                                                                   240 0  0    0
 1.50380+04 3.76578+01          0          0          0          2 240 8457    1
 6.40000-01 1.40000-01          0          0          6          0 240 8457    2
 4.29000+06 4.88353+05 2.77790+06 2.44192+05 3.22139+03 3.69035+02 240 8457    3
-7.77770+01 0.00000+00          0          0          6          1 240 8457    4
 1.00000+00 0.00000+00 1.23900+07 1.40000+05 1.00000+00 0.00000+00 240 8457    5
 0.00000+00 0.00000+00          0          0          6          5 240 8457    6
 1.00000-02 0.00000+00 2.77790+06 2.44192+05 0.00000+00 0.00000+00 240 8457    7
 1.29200+06 0.00000+00          0          0         12          0 240 8457    8
 1.00000+00 0.00000+00 8.85000+01 7.71726+00 0.00000+00 0.00000+00 240 8457    9
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 240 8457   10
 2.22430+06 0.00000+00          0          0         12          0 240 8457   11
 1.00000+00 0.00000+00 2.03550+01 3.76703+00 0.00000+00 0.00000+00 240 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 240 8457   13
 3.51620+06 0.00000+00          0          0         12          0 240 8457   14
 1.00000+00 0.00000+00 1.15050+01 3.61408+00 0.00000+00 0.00000+00 240 8457   15
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 240 8457   16
 3.69830+06 0.00000+00          0          0         12          0 240 8457   17
 1.00000+00 0.00000+00 9.73500+00 2.72552+00 0.00000+00 0.00000+00 240 8457   18
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 240 8457   19
 4.71360+06 0.00000+00          0          0         12          0 240 8457   20
 1.00000+00 0.00000+00 8.85000+00 2.71342+00 0.00000+00 0.00000+00 240 8457   21
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 240 8457   22
 0.00000+00 1.00000+00          0          0          6          4 240 8457   23
 1.00000-02 0.00000+00 4.29000+06 4.88353+05 0.00000+00 0.00000+00 240 8457   24
 6.38192+06 1.39956+05          0          0          6          0 240 8457   25
 1.00000+00 1.00000+00 1.00000+01 3.00000+00 0.00000+00 0.00000+00 240 8457   26
 7.39697+06 1.39956+05          0          0          6          0 240 8457   27
 1.00000+00 1.00000+00 1.10000+01 3.00000+00 0.00000+00 0.00000+00 240 8457   28
 8.87057+06 1.39954+05          0          0          6          0 240 8457   29
 1.00000+00 1.00000+00 3.60000+01 6.00000+00 0.00000+00 0.00000+00 240 8457   30
 1.10942+07 1.39952+05          0          0          6          0 240 8457   31
 1.00000+00 1.00000+00 4.30000+01 8.00000+00 0.00000+00 0.00000+00 240 8457   32
                                                                   240 8  099999
                                                                   240 0  0    0
                                                                     0 0  0    0
 1.503900+4 3.865130+1         -1          0          2          1 241 1451    1
 0.000000+0 1.000000+0          0          0          0          6 241 1451    2
 0.000000+0 0.000000+0          0          0          4        311 241 1451    3
 0.000000+0 0.000000+0          0          0         18          2 241 1451    4
 15-P - 39 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  241 1451    5
                      DIST-NOV07                       261107      241 1451    6
----JEFF-311          MATERIAL  241                                241 1451    7
-----RADIOACTIVE DECAY DATA                                        241 1451    8
------ENDF-6 FORMAT                                                241 1451    9
****************************************************************** 241 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 241 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 241 1451   12
**             Original data taken from:  NUBASE                ** 241 1451   13
****************************************************************** 241 1451   14
****************************************************************** 241 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 241 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      241 1451   17
                                                                   241 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           241 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        241 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               241 1451   21
****************************************************************** 241 1451   22
                                1        451         24          0 241 1451   23
                                8        457          6          0 241 1451   24
 0.000000+0 0.000000+0          0          0          0          0 241 1  099999
                                                                   241 0  0    0
 1.50390+04 3.86513+01          0          0          0          0 241 8457    1
 1.90000-01 5.00000-02          0          0          6          0 241 8457    2
 2.92298+06 0.00000+00 2.92298+06 0.00000+00 3.84781+05 0.00000+00 241 8457    3
 5.00000-01 1.00000+00          0          0         12          2 241 8457    4
 1.00000+00 0.00000+00 1.02900+07 0.00000+00 7.40000-01 0.00000+00 241 8457    5
 1.50000+00 0.00000+00 5.91970+06 0.00000+00 2.60000-01 0.00000+00 241 8457    6
                                                                   241 8  099999
                                                                   241 0  0    0
                                                                     0 0  0    0
 1.504000+4 3.964770+1         -1          0          2          1 242 1451    1
 0.000000+0 1.000000+0          0          0          0          6 242 1451    2
 0.000000+0 0.000000+0          0          0          4        311 242 1451    3
 0.000000+0 0.000000+0          0          0         18          2 242 1451    4
 15-P - 40 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  242 1451    5
                      DIST-NOV07                       261107      242 1451    6
----JEFF-311          MATERIAL  242                                242 1451    7
-----RADIOACTIVE DECAY DATA                                        242 1451    8
------ENDF-6 FORMAT                                                242 1451    9
****************************************************************** 242 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 242 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 242 1451   12
**             Original data taken from:  NUBASE                ** 242 1451   13
****************************************************************** 242 1451   14
****************************************************************** 242 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 242 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      242 1451   17
                                                                   242 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           242 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        242 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               242 1451   21
****************************************************************** 242 1451   22
                                1        451         24          0 242 1451   23
                                8        457          6          0 242 1451   24
 0.000000+0 0.000000+0          0          0          0          0 242 1  099999
                                                                   242 0  0    0
 1.50400+04 3.96477+01          0          0          0          0 242 8457    1
 1.50000-01 8.00000-03          0          0          6          0 242 8457    2
 4.41830+06 0.00000+00 4.41830+06 0.00000+00 2.75659+05 0.00000+00 242 8457    3
-7.77770+01 0.00000+00          0          0         12          2 242 8457    4
 1.00000+00 0.00000+00 1.47600+07 0.00000+00 8.42000-01 0.00000+00 242 8457    5
 1.50000+00 0.00000+00 6.97870+06 0.00000+00 1.58000-01 0.00000+00 242 8457    6
                                                                   242 8  099999
                                                                   242 0  0    0
                                                                     0 0  0    0
 1.504100+4 4.064220+1         -1          0          2          1 243 1451    1
 0.000000+0 1.000000+0          0          0          0          6 243 1451    2
 0.000000+0 0.000000+0          0          0          4        311 243 1451    3
 0.000000+0 0.000000+0          0          0         18          2 243 1451    4
 15-P - 41 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  243 1451    5
                      DIST-NOV07                       261107      243 1451    6
----JEFF-311          MATERIAL  243                                243 1451    7
-----RADIOACTIVE DECAY DATA                                        243 1451    8
------ENDF-6 FORMAT                                                243 1451    9
****************************************************************** 243 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 243 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 243 1451   12
**             Original data taken from:  NUBASE                ** 243 1451   13
****************************************************************** 243 1451   14
****************************************************************** 243 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 243 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      243 1451   17
                                                                   243 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           243 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        243 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               243 1451   21
****************************************************************** 243 1451   22
                                1        451         24          0 243 1451   23
                                8        457          6          0 243 1451   24
 0.000000+0 0.000000+0          0          0          0          0 243 1  099999
                                                                   243 0  0    0
 1.50410+04 4.06422+01          0          0          0          0 243 8457    1
 1.50000-01 1.50000-02          0          0          6          0 243 8457    2
 3.91990+06 0.00000+00 3.91990+06 0.00000+00 7.13903+05 0.00000+00 243 8457    3
 5.00000-01 1.00000+00          0          0         12          2 243 8457    4
 1.00000+00 0.00000+00 1.37400+07 0.00000+00 7.00000-01 0.00000+00 243 8457    5
 1.50000+00 0.00000+00 9.51870+06 0.00000+00 3.00000-01 0.00000+00 243 8457    6
                                                                   243 8  099999
                                                                   243 0  0    0
                                                                     0 0  0    0
 1.504200+4 4.164020+1         -1          0          2          1 244 1451    1
 0.000000+0 1.000000+0          0          0          0          6 244 1451    2
 0.000000+0 0.000000+0          0          0          4        311 244 1451    3
 0.000000+0 0.000000+0          0          0         18          2 244 1451    4
 15-P - 42 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  244 1451    5
                      DIST-NOV07                       261107      244 1451    6
----JEFF-311          MATERIAL  244                                244 1451    7
-----RADIOACTIVE DECAY DATA                                        244 1451    8
------ENDF-6 FORMAT                                                244 1451    9
****************************************************************** 244 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 244 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 244 1451   12
**             Original data taken from:  NUBASE                ** 244 1451   13
****************************************************************** 244 1451   14
****************************************************************** 244 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 244 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      244 1451   17
                                                                   244 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           244 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        244 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               244 1451   21
****************************************************************** 244 1451   22
                                1        451         24          0 244 1451   23
                                8        457          6          0 244 1451   24
 0.000000+0 0.000000+0          0          0          0          0 244 1  099999
                                                                   244 0  0    0
 1.50420+04 4.16402+01          0          0          0          0 244 8457    1
 1.20000-01 3.00000-02          0          0          6          0 244 8457    2
 4.58942+06 0.00000+00 4.58942+06 0.00000+00 1.48609+06 0.00000+00 244 8457    3
-7.77770+01 0.00000+00          0          0         12          2 244 8457    4
 1.00000+00 0.00000+00 1.86200+07 0.00000+00 5.00000-01 0.00000+00 244 8457    5
 1.50000+00 0.00000+00 1.18887+07 0.00000+00 5.00000-01 0.00000+00 244 8457    6
                                                                   244 8  099999
                                                                   244 0  0    0
                                                                     0 0  0    0
 1.504300+4 4.263680+1         -1          0          2          1 245 1451    1
 0.000000+0 1.000000+0          0          0          0          6 245 1451    2
 0.000000+0 0.000000+0          0          0          4        311 245 1451    3
 0.000000+0 0.000000+0          0          0         18          2 245 1451    4
 15-P - 43 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  245 1451    5
                      DIST-NOV07                       261107      245 1451    6
----JEFF-311          MATERIAL  245                                245 1451    7
-----RADIOACTIVE DECAY DATA                                        245 1451    8
------ENDF-6 FORMAT                                                245 1451    9
****************************************************************** 245 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 245 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 245 1451   12
**             Original data taken from:  NUBASE                ** 245 1451   13
****************************************************************** 245 1451   14
****************************************************************** 245 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 245 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      245 1451   17
                                                                   245 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           245 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        245 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               245 1451   21
****************************************************************** 245 1451   22
                                1        451         24          0 245 1451   23
                                8        457          5          0 245 1451   24
 0.000000+0 0.000000+0          0          0          0          0 245 1  099999
                                                                   245 0  0    0
 1.50430+04 4.26368+01          0          0          0          0 245 8457    1
 3.30000-02 3.00000-03          0          0          6          0 245 8457    2
 3.84468+06 0.00000+00 3.84468+06 0.00000+00 3.84468+06 0.00000+00 245 8457    3
 5.00000-01 1.00000+00          0          0          6          1 245 8457    4
 1.50000+00 0.00000+00 1.53787+07 0.00000+00 1.00000+00 0.00000+00 245 8457    5
                                                                   245 8  099999
                                                                   245 0  0    0
                                                                     0 0  0    0
 1.504400+4 4.363490+1         -1          0          2          1 246 1451    1
 0.000000+0 1.000000+0          0          0          0          6 246 1451    2
 0.000000+0 0.000000+0          0          0          4        311 246 1451    3
 0.000000+0 0.000000+0          0          0         18          2 246 1451    4
 15-P - 44 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  246 1451    5
                      DIST-NOV07                       261107      246 1451    6
----JEFF-311          MATERIAL  246                                246 1451    7
-----RADIOACTIVE DECAY DATA                                        246 1451    8
------ENDF-6 FORMAT                                                246 1451    9
****************************************************************** 246 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 246 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 246 1451   12
**             Original data taken from:  NUBASE                ** 246 1451   13
****************************************************************** 246 1451   14
****************************************************************** 246 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 246 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      246 1451   17
                                                                   246 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           246 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        246 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               246 1451   21
****************************************************************** 246 1451   22
                                1        451         24          0 246 1451   23
                                8        457          5          0 246 1451   24
 0.000000+0 0.000000+0          0          0          0          0 246 1  099999
                                                                   246 0  0    0
 1.50440+04 4.36349+01          0          0          0          0 246 8457    1
 3.00000-02 0.00000+00          0          0          6          0 246 8457    2
 7.07333+06 0.00000+00 7.07333+06 0.00000+00 0.00000+00 0.00000+00 246 8457    3
-7.77770+01 0.00000+00          0          0          6          1 246 8457    4
 1.00000+00 0.00000+00 2.12200+07 0.00000+00 1.00000+00 0.00000+00 246 8457    5
                                                                   246 8  099999
                                                                   246 0  0    0
                                                                     0 0  0    0
 1.504500+4 4.463250+1         -1          0          2          1 247 1451    1
 0.000000+0 1.000000+0          0          0          0          6 247 1451    2
 0.000000+0 0.000000+0          0          0          4        311 247 1451    3
 0.000000+0 0.000000+0          0          0         18          2 247 1451    4
 15-P - 45 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  247 1451    5
                      DIST-NOV07                       261107      247 1451    6
----JEFF-311          MATERIAL  247                                247 1451    7
-----RADIOACTIVE DECAY DATA                                        247 1451    8
------ENDF-6 FORMAT                                                247 1451    9
****************************************************************** 247 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 247 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 247 1451   12
**             Original data taken from:  NUBASE                ** 247 1451   13
****************************************************************** 247 1451   14
****************************************************************** 247 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 247 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      247 1451   17
                                                                   247 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           247 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        247 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               247 1451   21
****************************************************************** 247 1451   22
                                1        451         24          0 247 1451   23
                                8        457          5          0 247 1451   24
 0.000000+0 0.000000+0          0          0          0          0 247 1  099999
                                                                   247 0  0    0
 1.50450+04 4.46325+01          0          0          0          0 247 8457    1
 8.00000-03 0.00000+00          0          0          6          0 247 8457    2
 7.05000+06 0.00000+00 7.05000+06 0.00000+00 0.00000+00 0.00000+00 247 8457    3
 5.00000-01 1.00000+00          0          0          6          1 247 8457    4
 1.00000+00 0.00000+00 2.11500+07 0.00000+00 1.00000+00 0.00000+00 247 8457    5
                                                                   247 8  099999
                                                                   247 0  0    0
                                                                     0 0  0    0
 1.504600+4 4.563200+1         -1          0          2          1 248 1451    1
 0.000000+0 1.000000+0          0          0          0          6 248 1451    2
 0.000000+0 0.000000+0          0          0          4        311 248 1451    3
 0.000000+0 0.000000+0          0          0         18          2 248 1451    4
 15-P - 46 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  248 1451    5
                      DIST-NOV07                       261107      248 1451    6
----JEFF-311          MATERIAL  248                                248 1451    7
-----RADIOACTIVE DECAY DATA                                        248 1451    8
------ENDF-6 FORMAT                                                248 1451    9
****************************************************************** 248 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 248 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 248 1451   12
**             Original data taken from:  NUBASE                ** 248 1451   13
****************************************************************** 248 1451   14
****************************************************************** 248 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 248 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      248 1451   17
                                                                   248 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           248 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        248 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               248 1451   21
****************************************************************** 248 1451   22
                                1        451         24          0 248 1451   23
                                8        457          5          0 248 1451   24
 0.000000+0 0.000000+0          0          0          0          0 248 1  099999
                                                                   248 0  0    0
 1.50460+04 4.56320+01          0          0          0          0 248 8457    1
 4.00000-03 0.00000+00          0          0          6          0 248 8457    2
 8.26667+06 0.00000+00 8.26667+06 0.00000+00 0.00000+00 0.00000+00 248 8457    3
-7.77770+01 0.00000+00          0          0          6          1 248 8457    4
 1.00000+00 0.00000+00 2.48000+07 0.00000+00 1.00000+00 0.00000+00 248 8457    5
                                                                   248 8  099999
                                                                   248 0  0    0
                                                                     0 0  0    0
