 1.101800+4 1.787110+1         -1          0          2          1 137 1451    1
 0.000000+0 1.000000+0          0          0          0          6 137 1451    2
 0.000000+0 0.000000+0          0          0          4        311 137 1451    3
 0.000000+0 0.000000+0          0          0         18          2 137 1451    4
 11-Na- 18 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  137 1451    5
                      DIST-NOV07                       261107      137 1451    6
----JEFF-311          MATERIAL  137                                137 1451    7
-----RADIOACTIVE DECAY DATA                                        137 1451    8
------ENDF-6 FORMAT                                                137 1451    9
****************************************************************** 137 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 137 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 137 1451   12
**             Original data taken from:  NUBASE                ** 137 1451   13
****************************************************************** 137 1451   14
****************************************************************** 137 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 137 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      137 1451   17
                                                                   137 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           137 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        137 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               137 1451   21
****************************************************************** 137 1451   22
                                1        451         24          0 137 1451   23
                                8        457          6          0 137 1451   24
 0.000000+0 0.000000+0          0          0          0          0 137 1  099999
                                                                   137 0  0    0
 1.10180+04 1.78711+01          0          0          0          0 137 8457    1
 1.30000-21 4.00000-22          0          0          6          0 137 8457    2
 3.14547+06 0.00000+00 3.14547+06 0.00000+00 2.20000+05 0.00000+00 137 8457    3
 1.00000+00-1.00000+00          0          0         12          2 137 8457    4
 7.00000+00 0.00000+00 4.40000+05 0.00000+00 5.00000-01 0.00000+00 137 8457    5
 2.00000+00 0.00000+00 1.88728+07 0.00000+00 5.00000-01 0.00000+00 137 8457    6
                                                                   137 8  099999
                                                                   137 0  0    0
                                                                     0 0  0    0
 1.101900+4 1.885050+1         -1          0          2          1 138 1451    1
 0.000000+0 1.000000+0          0          0          0          6 138 1451    2
 0.000000+0 0.000000+0          0          0          4        311 138 1451    3
 0.000000+0 0.000000+0          0          0         18          2 138 1451    4
 11-Na- 19 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  138 1451    5
                      DIST-NOV07                       261107      138 1451    6
----JEFF-311          MATERIAL  138                                138 1451    7
-----RADIOACTIVE DECAY DATA                                        138 1451    8
------ENDF-6 FORMAT                                                138 1451    9
****************************************************************** 138 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 138 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 138 1451   12
**             Original data taken from:  NUBASE                ** 138 1451   13
****************************************************************** 138 1451   14
****************************************************************** 138 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 138 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      138 1451   17
                                                                   138 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           138 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        138 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               138 1451   21
****************************************************************** 138 1451   22
                                1        451         24          0 138 1451   23
                                8        457          5          0 138 1451   24
 0.000000+0 0.000000+0          0          0          0          0 138 1  099999
                                                                   138 0  0    0
 1.10190+04 1.88505+01          0          0          0          0 138 8457    1
 4.00000-08 0.00000+00          0          0          6          0 138 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 3.20831+05 0.00000+00 138 8457    3
 2.50000+00 1.00000+00          0          0          6          1 138 8457    4
 7.00000+00 0.00000+00 3.20831+05 0.00000+00 1.00000+00 0.00000+00 138 8457    5
                                                                   138 8  099999
                                                                   138 0  0    0
                                                                     0 0  0    0
 1.102000+4 1.983550+1         -1          0          2          1 139 1451    1
 0.000000+0 1.000000+0          0          0          0          6 139 1451    2
 0.000000+0 0.000000+0          0          0          4        311 139 1451    3
 0.000000+0 0.000000+0          0          0         18          2 139 1451    4
 11-Na- 20 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  139 1451    5
                      DIST-NOV07                       261107      139 1451    6
----JEFF-311          MATERIAL  139                                139 1451    7
-----RADIOACTIVE DECAY DATA                                        139 1451    8
------ENDF-6 FORMAT                                                139 1451    9
****************************************************************** 139 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 139 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 139 1451   12
**             Original data taken from:  NUBASE                ** 139 1451   13
****************************************************************** 139 1451   14
****************************************************************** 139 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 139 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      139 1451   17
                                                                   139 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           139 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        139 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               139 1451   21
****************************************************************** 139 1451   22
                                1        451         24          0 139 1451   23
                                8        457          6          0 139 1451   24
 0.000000+0 0.000000+0          0          0          0          0 139 1  099999
                                                                   139 0  0    0
 1.10200+04 1.98355+01          0          0          0          0 139 8457    1
 4.47900-01 2.30000-03          0          0          6          0 139 8457    2
 4.04499+06 0.00000+00 4.04499+06 0.00000+00 5.72506+05 0.00000+00 139 8457    3
 2.00000+00 1.00000+00          0          0         12          2 139 8457    4
 2.00000+00 0.00000+00 1.38899+07 0.00000+00 7.50000-01 0.00000+00 139 8457    5
 2.40000+00 0.00000+00 9.16010+06 0.00000+00 2.50000-01 0.00000+00 139 8457    6
                                                                   139 8  099999
                                                                   139 0  0    0
                                                                     0 0  0    0
 1.102100+4 2.081730+1         -1          0          2          1 140 1451    1
 0.000000+0 1.000000+0          0          0          0          6 140 1451    2
 0.000000+0 0.000000+0          0          0          4        311 140 1451    3
 0.000000+0 0.000000+0          0          0         47          2 140 1451    4
 11-Na- 21 ENSDF      EVAL-APR00 CONVERSION OF ENSDF               140 1451    5
 /ENSDF/              DIST-NOV07                       261107      140 1451    6
----JEFF-311          MATERIAL  140                                140 1451    7
-----RADIOACTIVE DECAY DATA                                        140 1451    8
------ENDF-6 FORMAT                                                140 1451    9
****************************************************************** 140 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 140 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 140 1451   12
**             Original data taken from:  ENSDF                 ** 140 1451   13
****************************************************************** 140 1451   14
****************************************************************** 140 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 140 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 140 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 140 1451   18
****************************************************************** 140 1451   19
21NA  DECAY 22.49 S   4                     I(min) = 0.0E+00 %     140 1451   20
         Ex = 0.0         keV                     1 decay mode(s)  140 1451   21
                                                                   140 1451   22
21NA B+ DECAY               Q =  3547.5000 keV       0.7000        140 1451   23
         Branching                100.0000 %         0.0000        140 1451   24
                         Br*Q =  3547.5000 keV       0.7000        140 1451   25
                                              0 isomeric state(s)  140 1451   26
                                                                   140 1451   27
Individual beta+ transitions                                       140 1451   28
Final level    end point    shape    av.energy        intensity    140 1451   29
  350.720   2174.387   0.702  0    944.800   0.600    5.020 0.130  140 1451   30
    0.000   2525.044   0.700  0   1110.300   0.600   94.880 0.130  140 1451   31
                                                                   140 1451   32
         Mean alpha    energy       0.0000 keV       0.0000        140 1451   33
         Mean beta     energy    1100.8816 keV       1.9791        140 1451   34
         Mean conv. e- energy       0.0000 keV       0.0000        140 1451   35
         Mean Auger e- energy       0.0000 keV       0.0000        140 1451   36
         Mean gamma    energy    1037.1092 keV                     140 1451   37
         Mean X        energy       0.0000 keV       0.0000        140 1451   38
         Mean recoil   energy       0.4544 keV       0.0008        140 1451   39
         Mean neutrino energy    1407.4762 keV       2.5261        140 1451   40
         Mean neutron  energy       0.0000 keV       0.0000        140 1451   41
         Total         energy    3545.9216 keV       4.1114        140 1451   42
         Q effective             3547.5000 keV       0.7000        140 1451   43
         diff. mode                -1.5784 keV      -0.0445 %      140 1451   44
                                                                   140 1451   45
         Mean e- bind. energy       0.0000 keV                     140 1451   46
         diff. atomic               0.0000 keV     -93.0891 %      140 1451   47
         diff. nuclear             -1.5784 keV      -0.0445 %      140 1451   48
                                                                   140 1451   49
         B+ fraction               99.9000 %         0.1838        140 1451   50
                                                                   140 1451   51
                                1        451         53          0 140 1451   52
                                8        457         28          0 140 1451   53
 0.000000+0 0.000000+0          0          0          0          0 140 1  099999
                                                                   140 0  0    0
 1.10210+04 2.08173+01          0          0          0          4 140 8457    1
 2.24900+01 4.00000-02          0          0          6          0 140 8457    2
 1.10088+06 1.97912+03 1.03711+06 2.57011+03 0.00000+00 0.00000+00 140 8457    3
 1.50000+00 1.00000+00          0          0          6          1 140 8457    4
 2.00000+00 0.00000+00 3.54750+06 7.00000+02 1.00000+00 0.00000+00 140 8457    5
 0.00000+00 0.00000+00          0          0          6          1 140 8457    6
 1.00000-02 0.00000+00 1.61331+04 1.75360+03 0.00000+00 0.00000+00 140 8457    7
 3.50720+05 6.00000+01          0          0         12          0 140 8457    8
 2.00000+00 0.00000+00 4.60000+00 5.00000-01 0.00000+00 0.00000+00 140 8457    9
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 140 8457   10
 0.00000+00 2.00000+00          0          0          6          3 140 8457   11
 1.00000-02 0.00000+00 1.10088+06 1.97912+03 0.00000+00 0.00000+00 140 8457   12
 7.53360+05 7.01783+02          0          0          6          0 140 8457   13
 2.00000+00 1.00000+00 4.00000-04 8.00000-05 0.00000+00 0.00000+00 140 8457   14
 3.19620+06 7.02439+02          0          0          6          0 140 8457   15
 2.00000+00 1.00000+00 5.03000+00 1.30000-01 5.02000+00 1.30000-01 140 8457   16
 3.54686+06 6.99873+02          0          0          6          0 140 8457   17
 2.00000+00 1.00000+00 9.49700+01 1.30000-01 9.48800+01 1.30000-01 140 8457   18
 0.00000+00 8.00000+00          0          0          6          1 140 8457   19
 1.00000-02 0.00000+00 2.98519-03 5.97167-04 0.00000+00 0.00000+00 140 8457   20
 8.20000+02 0.00000+00          0          0          6          0 140 8457   21
 2.00000+00 0.00000+00 3.64047-04 7.28252-05 0.00000+00 0.00000+00 140 8457   22
 0.00000+00 9.00000+00          0          0          6          2 140 8457   23
 1.00000-02 0.00000+00 1.02098+06 2.30120+03 0.00000+00 0.00000+00 140 8457   24
 8.48600+02 2.00000-01          0          0          6          0 140 8457   25
 2.00000+00 0.00000+00 4.94449-06 1.80740-06 0.00000+00 0.00000+00 140 8457   26
 5.10999+05 1.50000-01          0          0          6          0 140 8457   27
 2.00000+00 0.00000+00 1.99800+02 4.50333-01 0.00000+00 0.00000+00 140 8457   28
                                                                   140 8  099999
                                                                   140 0  0    0
                                                                     0 0  0    0
 1.102200+4 2.180550+1         -1          0          2          1 141 1451    1
 0.000000+0 1.000000+0          0          0          0          6 141 1451    2
 0.000000+0 0.000000+0          0          0          4        311 141 1451    3
 0.000000+0 0.000000+0          0          0         50          2 141 1451    4
 11-Na- 22 INL+PTB    EVAL-FEB98 R.G.HELMER, E.SCHONFELD           141 1451    5
 /DDEP/               DIST-NOV07                       261107      141 1451    6
----JEFF-311          MATERIAL  141                                141 1451    7
-----RADIOACTIVE DECAY DATA                                        141 1451    8
------ENDF-6 FORMAT                                                141 1451    9
****************************************************************** 141 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 141 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 141 1451   12
**             Original data taken from:  LNHB                  ** 141 1451   13
****************************************************************** 141 1451   14
****************************************************************** 141 1451   15
*Data from the Laboratoire National Henri Becquerel, BNM-CEA/LNHB* 141 1451   16
*              http://www.nucleide.org/NucData.htm               * 141 1451   17
****************************************************************** 141 1451   18
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 141 1451   19
*     (the CEA-Bruyeres version of the RADLST program).          * 141 1451   20
* (1) 0. Bersillon and J. Blachot, to be published.              * 141 1451   21
****************************************************************** 141 1451   22
DECAY 2.6027 Y  10                    I(min) = 0.0E+00 %           141 1451   23
         Ex = 0.0         keV                     1 decay mode(s)  141 1451   24
                                                                   141 1451   25
 22NA EC DECAY              Q =  2842.2000 keV       0.4000        141 1451   26
         Branching                100.0000 %         0.0000        141 1451   27
                         Br*Q =  2842.2000 keV       0.4000        141 1451   28
                                              0 isomeric state(s)  141 1451   29
                                                                   141 1451   30
Individual beta+ transitions                                       141 1451   31
Final level    end point    shape    av.energy        intensity    141 1451   32
 1274.577    545.549   0.400  0    215.600   0.200   89.836 0.010  141 1451   33
    0.000   1819.949   0.400  0    779.500   0.200    0.056 0.014  141 1451   34
                                                                   141 1451   35
         Mean alpha    energy       0.0000 keV       0.0000        141 1451   36
         Mean beta     energy     194.1229 keV       0.2113        141 1451   37
         Mean conv. e- energy       0.0080 keV       0.0008        141 1451   38
         Mean Auger e- energy       0.0755 keV       0.0005        141 1451   39
         Mean gamma    energy    2192.4668 keV                     141 1451   40
         Mean X        energy       0.0011 keV       0.0003        141 1451   41
         Mean recoil   energy       0.0682 keV       0.0001        141 1451   42
         Mean neutrino energy     455.4297 keV       1.7682        141 1451   43
         Mean neutron  energy       0.0000 keV       0.0000        141 1451   44
         Total         energy    2842.2118 keV       1.7984        141 1451   45
         Q effective             2842.2000 keV       0.4000        141 1451   46
         diff. mode                 0.0118 keV       0.0004 %      141 1451   47
                                                                   141 1451   48
         Mean e- bind. energy       0.0813 keV                     141 1451   49
         diff. atomic              -0.0047 keV      -5.7739 %      141 1451   50
         diff. nuclear              0.0165 keV       0.0006 %      141 1451   51
                                                                   141 1451   52
         B+ fraction               89.8920 %         0.0172        141 1451   53
                                                                   141 1451   54
                                1        451         56          0 141 1451   55
                                8        457         28          0 141 1451   56
 0.000000+0 0.000000+0          0          0          0          0 141 1  099999
                                                                   141 0  0    0
 1.10220+04 2.18055+01          0          0          0          4 141 8457    1
 8.21332+07 3.15569+04          0          0          6          0 141 8457    2
 1.94206+05 2.11322+02 2.19247+06 2.50609+02 0.00000+00 0.00000+00 141 8457    3
 3.00000+00 1.00000+00          0          0          6          1 141 8457    4
 2.00000+00 0.00000+00 2.84220+06 4.00000+02 1.00000+00 0.00000+00 141 8457    5
 0.00000+00 0.00000+00          0          0          6          1 141 8457    6
 1.00000-02 0.00000+00 1.27377+06 1.78572+02 0.00000+00 0.00000+00 141 8457    7
 1.27454+06 7.00000+00          0          0         12          0 141 8457    8
 2.00000+00 0.00000+00 9.99400+01 1.40000-02 0.00000+00 0.00000+00 141 8457    9
 6.80000-06 4.00000-07 6.30000-06 6.29064-07 0.00000+00 0.00000+00 141 8457   10
 0.00000+00 2.00000+00          0          0          6          2 141 8457   11
 1.00000-02 0.00000+00 1.94123+05 2.11320+02 0.00000+00 0.00000+00 141 8457   12
 1.56741+06 4.00006+02          0          0          6          0 141 8457   13
 2.00000+00 1.00000+00 9.99460+01 1.10454-01 8.98360+01 1.00000-02 141 8457   14
 2.84181+06 3.99945+02          0          0          6          0 141 8457   15
 2.00000+00 1.00000+00 5.70000-02 1.40032-02 5.60000-02 1.40000-02 141 8457   16
 0.00000+00 8.00000+00          0          0          6          2 141 8457   17
 1.00000-02 0.00000+00 8.35176+01 9.23915-01 0.00000+00 0.00000+00 141 8457   18
 8.20000+02 0.00000+00          0          0          6          0 141 8457   19
 2.00000+00 0.00000+00 9.20711+00 5.62081-02 0.00000+00 0.00000+00 141 8457   20
 1.27367+06 7.00643+00          0          0          6          0 141 8457   21
 2.00000+00 0.00000+00 6.29622-04 6.28687-05 0.00000+00 0.00000+00 141 8457   22
 0.00000+00 9.00000+00          0          0          6          2 141 8457   23
 1.00000-02 0.00000+00 9.18696+05 2.02346+02 0.00000+00 0.00000+00 141 8457   24
 8.48600+02 2.00000-01          0          0          6          0 141 8457   25
 2.00000+00 0.00000+00 1.25051-01 3.82659-02 0.00000+00 0.00000+00 141 8457   26
 5.10999+05 1.50000-01          0          0          6          0 141 8457   27
 2.00000+00 0.00000+00 1.79784+02 3.95980-02 0.00000+00 0.00000+00 141 8457   28
                                                                   141 8  099999
                                                                   141 0  0    0
                                                                     0 0  0    0
 1.102300+4 2.279230+1         -1          0          2          1 142 1451    1
 0.000000+0 0.000000+0          0          0          0          6 142 1451    2
 0.000000+0 0.000000+0          0          0          4        311 142 1451    3
 0.000000+0 0.000000+0          0          0         22          2 142 1451    4
 11-Na- 23 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  142 1451    5
                      DIST-NOV07                       261107      142 1451    6
----JEFF-311          MATERIAL  142                                142 1451    7
-----RADIOACTIVE DECAY DATA                                        142 1451    8
------ENDF-6 FORMAT                                                142 1451    9
****************************************************************** 142 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 142 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 142 1451   12
**             Original data taken from:  NUBASE                ** 142 1451   13
****************************************************************** 142 1451   14
****************************************************************** 142 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 142 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      142 1451   17
                                                                   142 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           142 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        142 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               142 1451   21
****************************************************************** 142 1451   22
STABLE NUCLEUS                                                     142 1451   23
       SPIN          1.5                                           142 1451   24
       PARITY        1.0                                           142 1451   25
NATURAL ABUNDANCE  100.          %                                 142 1451   26
                                1        451         28          0 142 1451   27
                                8        457          5          0 142 1451   28
 0.000000+0 0.000000+0          0          0          0          0 142 1  099999
                                                                   142 0  0    0
 1.10230+04 2.27923+01          0          0          1          0 142 8457    1
 0.00000+00 0.00000+00          0          0          6          0 142 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 142 8457    3
 1.50000+00 1.00000+00          0          0          6          0 142 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 142 8457    5
                                                                   142 8  099999
                                                                   142 0  0    0
                                                                     0 0  0    0
 1.102400+4 2.378490+1         -1          0          2          1 143 1451    1
 0.000000+0 1.000000+0          0          0          0          6 143 1451    2
 0.000000+0 0.000000+0          0          0          4        311 143 1451    3
 0.000000+0 0.000000+0          0          0         50          2 143 1451    4
 11-Na- 24 INL        EVAL-NOV01 R.G.HELMER, E.SCHONFELD           143 1451    5
 /DDEP/               DIST-NOV07                       261107      143 1451    6
----JEFF-311          MATERIAL  143                                143 1451    7
-----RADIOACTIVE DECAY DATA                                        143 1451    8
------ENDF-6 FORMAT                                                143 1451    9
****************************************************************** 143 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 143 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 143 1451   12
**             Original data taken from:  LNHB                  ** 143 1451   13
****************************************************************** 143 1451   14
****************************************************************** 143 1451   15
*Data from the Laboratoire National Henri Becquerel, BNM-CEA/LNHB* 143 1451   16
*              http://www.nucleide.org/NucData.htm               * 143 1451   17
****************************************************************** 143 1451   18
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 143 1451   19
*     (the CEA-Bruyeres version of the RADLST program).          * 143 1451   20
* (1) 0. Bersillon and J. Blachot, to be published.              * 143 1451   21
****************************************************************** 143 1451   22
DECAY 14.9574 H 20                    I(min) = 0.0E+00 %           143 1451   23
         Ex = 0.0         keV                     1 decay mode(s)  143 1451   24
                                                                   143 1451   25
 24NA B- DECAY              Q =  5515.7800 keV       0.1600        143 1451   26
         Branching                100.0000 %         0.0000        143 1451   27
                         Br*Q =  5515.7800 keV       0.1600        143 1451   28
                                              0 isomeric state(s)  143 1451   29
                                                                   143 1451   30
Individual beta- transitions                                       143 1451   31
Final level    end point    shape    av.energy        intensity    143 1451   32
 5236.500    279.211   0.525  0     89.500   0.200    0.057 0.007  143 1451   33
 4238.300   1277.165   0.189  1    531.480   0.080    0.001 0.001  143 1451   34
 4122.845   1392.591   0.160  0    554.970   0.080   99.939 0.008  143 1451   35
 1368.668   4146.088   0.160  1   1882.800   0.080    0.003 0.002  143 1451   36
                                                                   143 1451   37
         Mean alpha    energy       0.0000 keV       0.0000        143 1451   38
         Mean beta     energy     554.7443 keV       0.0992        143 1451   39
         Mean conv. e- energy       0.0218 keV       0.0005        143 1451   40
         Mean Auger e- energy       0.0000 keV       0.0000        143 1451   41
         Mean gamma    energy    4121.2387 keV                     143 1451   42
         Mean X        energy       0.0000 keV       0.0000        143 1451   43
         Mean recoil   energy       0.3437 keV       0.0001        143 1451   44
         Mean neutrino energy     837.2937 keV       0.1147        143 1451   45
         Mean neutron  energy       0.0000 keV       0.0000        143 1451   46
         Total         energy    5513.8539 keV       0.3808        143 1451   47
         Q effective             5515.7800 keV       0.1600        143 1451   48
         diff. mode                -1.9261 keV      -0.0349 %      143 1451   49
                                                                   143 1451   50
         Mean e- bind. energy       0.0000 keV                     143 1451   51
         diff. atomic               0.0000 keV      -9.8127 %      143 1451   52
         diff. nuclear             -1.9261 keV      -0.0349 %      143 1451   53
                                                                   143 1451   54
                                1        451         56          0 143 1451   55
                                8        457         67          0 143 1451   56
 0.000000+0 0.000000+0          0          0          0          0 143 1  099999
                                                                   143 0  0    0
 1.10240+04 2.37849+01          0          0          0          4 143 8457    1
 5.38466+04 7.20000+00          0          0          6          0 143 8457    2
 5.54766+05 9.92423+01 4.12124+06 3.49285+02 0.00000+00 0.00000+00 143 8457    3
 4.00000+00 1.00000+00          0          0          6          1 143 8457    4
 1.00000+00 0.00000+00 5.51578+06 1.60000+02 1.00000+00 0.00000+00 143 8457    5
 0.00000+00 0.00000+00          0          0          6          6 143 8457    6
 1.00000-02 0.00000+00 4.12124+06 3.49285+02 0.00000+00 0.00000+00 143 8457    7
 9.96090+05 6.00000+01          0          0         12          0 143 8457    8
 1.00000+00 0.00000+00 1.23000-03 2.70000-04 0.00000+00 0.00000+00 143 8457    9
 1.70000-05 5.00000-06 1.60000-05 5.02299-06 1.00000-06 3.00000-08 143 8457   10
 1.36863+06 5.00000+00          0          0         12          0 143 8457   11
 1.00000+00 0.00000+00 9.99935+01 5.00000-04 0.00000+00 0.00000+00 143 8457   12
 1.04000-05 0.00000+00 9.80000-06 2.94000-07 6.00000-07 1.80000-08 143 8457   13
 2.75401+06 1.10000+01          0          0         12          0 143 8457   14
 1.00000+00 0.00000+00 9.98720+01 8.00000-03 0.00000+00 0.00000+00 143 8457   15
 2.80000-06 0.00000+00 2.60000-06 7.80000-08 1.70000-07 5.10000-09 143 8457   16
 2.86950+06 6.00000+01          0          0         12          0 143 8457   17
 1.00000+00 0.00000+00 2.40000-04 3.00000-05 0.00000+00 0.00000+00 143 8457   18
 2.70000-06 0.00000+00 2.50000-06 7.50000-08 1.60000-07 4.80000-09 143 8457   19
 3.86614+06 1.00000+02          0          0         12          0 143 8457   20
 1.00000+00 0.00000+00 5.60000-02 7.00000-03 0.00000+00 0.00000+00 143 8457   21
 1.50000-06 0.00000+00 1.40000-06 4.20000-08 1.00000-07 3.00000-09 143 8457   22
 4.23796+06 6.00000+01          0          0         12          0 143 8457   23
 1.00000+00 0.00000+00 8.40000-04 1.00000-04 0.00000+00 0.00000+00 143 8457   24
 1.60000-06 0.00000+00 1.50000-06 4.50000-08 1.00000-07 3.00000-09 143 8457   25
 0.00000+00 1.00000+00          0          0          6          4 143 8457   26
 1.00000-02 0.00000+00 5.54744+05 9.92413+01 0.00000+00 0.00000+00 143 8457   27
 2.79211+05 5.24847+02          0          0          6          0 143 8457   28
 1.00000+00 1.00000+00 5.70000-02 7.00000-03 0.00000+00 0.00000+00 143 8457   29
 1.27716+06 1.88633+02          0          0          6          0 143 8457   30
 1.00000+00 2.00000+00 1.00000-03 1.00000-03 0.00000+00 0.00000+00 143 8457   31
 1.39259+06 1.60410+02          0          0          6          0 143 8457   32
 1.00000+00 1.00000+00 9.99390+01 8.00000-03 0.00000+00 0.00000+00 143 8457   33
 4.14609+06 1.60039+02          0          0          6          0 143 8457   34
 1.00000+00 2.00000+00 3.00000-03 2.00000-03 0.00000+00 0.00000+00 143 8457   35
 0.00000+00 8.00000+00          0          0          6         13 143 8457   36
 1.00000-02 0.00000+00 2.18531+01 4.56469-01 0.00000+00 0.00000+00 143 8457   37
 1.18000+03 0.00000+00          0          0          6          0 143 8457   38
 1.00000+00 0.00000+00 1.20685-03 2.98714-05 0.00000+00 0.00000+00 143 8457   39
 9.94785+05 6.00013+01          0          0          6          0 143 8457   40
 1.00000+00 0.00000+00 1.96800-08 7.53880-09 0.00000+00 0.00000+00 143 8457   41
 9.96001+05 6.00013+01          0          0          6          0 143 8457   42
 1.00000+00 0.00000+00 1.23000-09 2.72510-10 0.00000+00 0.00000+00 143 8457   43
 1.36732+06 5.01597+00          0          0          6          0 143 8457   44
 1.00000+00 0.00000+00 9.79936-04 2.93981-05 0.00000+00 0.00000+00 143 8457   45
 1.36854+06 5.01597+00          0          0          6          0 143 8457   46
 1.00000+00 0.00000+00 5.99961-05 1.79988-06 0.00000+00 0.00000+00 143 8457   47
 2.75270+06 1.10073+01          0          0          6          0 143 8457   48
 1.00000+00 0.00000+00 2.59667-04 7.79004-06 0.00000+00 0.00000+00 143 8457   49
 2.75392+06 1.10073+01          0          0          6          0 143 8457   50
 1.00000+00 0.00000+00 1.69782-05 5.09349-07 0.00000+00 0.00000+00 143 8457   51
 2.86820+06 6.00013+01          0          0          6          0 143 8457   52
 1.00000+00 0.00000+00 6.00000-10 7.71298-11 0.00000+00 0.00000+00 143 8457   53
 2.86941+06 6.00013+01          0          0          6          0 143 8457   54
 1.00000+00 0.00000+00 3.84000-11 4.93630-12 0.00000+00 0.00000+00 143 8457   55
 3.86484+06 1.00001+02          0          0          6          0 143 8457   56
 1.00000+00 0.00000+00 7.84000-08 1.00783-08 0.00000+00 0.00000+00 143 8457   57
 3.86605+06 1.00001+02          0          0          6          0 143 8457   58
 1.00000+00 0.00000+00 5.60000-09 7.19878-10 0.00000+00 0.00000+00 143 8457   59
 4.23666+06 6.00013+01          0          0          6          0 143 8457   60
 1.00000+00 0.00000+00 1.26000-09 1.54689-10 0.00000+00 0.00000+00 143 8457   61
 4.23787+06 6.00013+01          0          0          6          0 143 8457   62
 1.00000+00 0.00000+00 8.40000-11 1.03126-11 0.00000+00 0.00000+00 143 8457   63
 0.00000+00 9.00000+00          0          0          6          1 143 8457   64
 1.00000-02 0.00000+00 4.11834-04 5.07470-05 0.00000+00 0.00000+00 143 8457   65
 1.25360+03 4.00000-01          0          0          6          0 143 8457   66
 1.00000+00 0.00000+00 3.28521-05 4.04809-06 0.00000+00 0.00000+00 143 8457   67
                                                                   143 8  099999
                                                                   143 0  0    0
                                                                     0 0  0    0
 1.102400+4 2.378490+1         -1          0          2          1 144 1451    1
 4.723000+5 1.000000+0          1          1          0          6 144 1451    2
 0.000000+0 0.000000+0          0          0          4        311 144 1451    3
 0.000000+0 0.000000+0          0          0         81          2 144 1451    4
 11-Na- 24MSAC        EVAL-JUL98 N.COURSOL                         144 1451    5
 /DDEP/               DIST-NOV07                       261107      144 1451    6
----JEFF-311          MATERIAL  144                                144 1451    7
-----RADIOACTIVE DECAY DATA                                        144 1451    8
------ENDF-6 FORMAT                                                144 1451    9
****************************************************************** 144 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 144 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 144 1451   12
**             Original data taken from:  LNHB                  ** 144 1451   13
****************************************************************** 144 1451   14
****************************************************************** 144 1451   15
*Data from the Laboratoire National Henri Becquerel, BNM-CEA/LNHB* 144 1451   16
*              http://www.nucleide.org/NucData.htm               * 144 1451   17
****************************************************************** 144 1451   18
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 144 1451   19
*     (the CEA-Bruyeres version of the RADLST program).          * 144 1451   20
* (1) 0. Bersillon and J. Blachot, to be published.              * 144 1451   21
****************************************************************** 144 1451   22
DECAY 0.0202 S  2      COMBINED DATA  I(min) = 0.0E+00 %           144 1451   23
         Ex = 472.3     4 keV                     2 decay mode(s)  144 1451   24
                                                                   144 1451   25
 24NA IT DECAY              Q =   472.3000 keV       0.0000        144 1451   26
         Branching                 99.5000 %         0.0000        144 1451   27
                         Br*Q =   469.9385 keV       0.0000        144 1451   28
                                              0 isomeric state(s)  144 1451   29
                                                                   144 1451   30
         Mean alpha    energy       0.0000 keV       0.0000        144 1451   31
         Mean beta     energy       0.0000 keV       0.0000        144 1451   32
         Mean conv. e- energy       0.0000 keV       0.0000        144 1451   33
         Mean Auger e- energy       0.0000 keV       0.0000        144 1451   34
         Mean gamma    energy     469.9268 keV                     144 1451   35
         Mean X        energy       0.0000 keV       0.0000        144 1451   36
         Mean recoil   energy       0.0000 keV       0.0000        144 1451   37
         Mean neutrino energy       0.0000 keV       0.0000        144 1451   38
         Mean neutron  energy       0.0000 keV       0.0000        144 1451   39
         Total         energy     469.9317 keV       2.3947        144 1451   40
         Q effective              469.9385 keV       0.0000        144 1451   41
         diff. mode                -0.0068 keV      -0.0014 %      144 1451   42
                                                                   144 1451   43
         Mean e- bind. energy       0.0000 keV                     144 1451   44
         diff. atomic               0.0000 keV       0.0000 %      144 1451   45
         diff. nuclear             -0.0068 keV      -0.0014 %      144 1451   46
                                                                   144 1451   47
 24NA B- DECAY              Q =  5988.1000 keV       0.7211        144 1451   48
         Branching                  0.5000 %         0.0000        144 1451   49
                         Br*Q =    29.9405 keV       0.0036        144 1451   50
                                              0 isomeric state(s)  144 1451   51
                                                                   144 1451   52
Individual beta- transitions                                       144 1451   53
Final level    end point    shape    av.energy        intensity    144 1451   54
    0.000   5986.622   0.721  0   2768.700   0.400    0.500 0.500  144 1451   55
                                                                   144 1451   56
         Mean alpha    energy       0.0000 keV       0.0000        144 1451   57
         Mean beta     energy      13.8435 keV      13.8435        144 1451   58
         Mean conv. e- energy       0.0000 keV       0.0000        144 1451   59
         Mean Auger e- energy       0.0000 keV       0.0000        144 1451   60
         Mean gamma    energy       0.0000 keV                     144 1451   61
         Mean X        energy       0.0000 keV       0.0000        144 1451   62
         Mean recoil   energy       0.0074 keV       0.0074        144 1451   63
         Mean neutrino energy      16.0896 keV      16.0896        144 1451   64
         Mean neutron  energy       0.0000 keV       0.0000        144 1451   65
         Total         energy      29.9405 keV      21.2254        144 1451   66
         Q effective               29.9405 keV       0.0036        144 1451   67
         diff. mode                 0.0000 keV       0.0000 %      144 1451   68
                                                                   144 1451   69
         Mean e- bind. energy       0.0000 keV                     144 1451   70
         diff. atomic               0.0000 keV       0.0000 %      144 1451   71
         diff. nuclear              0.0000 keV       0.0000 %      144 1451   72
                                                                   144 1451   73
 TOTAL DECAY                                                       144 1451   74
         Mean alpha    energy       0.0000 keV       0.0000        144 1451   75
         Mean beta     energy      13.8435 keV      13.8435        144 1451   76
         Mean CE+Auger energy       0.0000 keV       0.0000        144 1451   77
         Mean gamma+X  energy     469.9268 keV       2.3947        144 1451   78
         Mean recoil   energy       0.0074 keV       0.0074        144 1451   79
         Mean neutrino energy      16.0896 keV      16.0896        144 1451   80
         Mean neutron  energy       0.0000 keV       0.0000        144 1451   81
         Total         energy     499.8722 keV      21.3601        144 1451   82
         Q effective              499.8790 keV       0.0036        144 1451   83
         diff.                     -0.0068 keV      -0.0014 %      144 1451   84
                                                                   144 1451   85
                                1        451         87          0 144 1451   86
                                8        457         15          0 144 1451   87
 0.000000+0 0.000000+0          0          0          0          0 144 1  099999
                                                                   144 0  0    0
 1.10240+04 2.37849+01          1          1          0          2 144 8457    1
 2.02000-02 2.00000-04          0          0          6          0 144 8457    2
 1.38435+04 1.38435+04 4.69927+05 2.39474+03 0.00000+00 0.00000+00 144 8457    3
 1.00000+00 1.00000+00          0          0         12          2 144 8457    4
 3.00000+00 0.00000+00 4.72300+05 0.00000+00 9.95000-01 0.00000+00 144 8457    5
 1.00000+00 0.00000+00 5.98810+06 7.21110+02 5.00000-03 0.00000+00 144 8457    6
 0.00000+00 0.00000+00          0          0          6          1 144 8457    7
 1.00000-02 0.00000+00 4.69927+05 2.39474+03 0.00000+00 0.00000+00 144 8457    8
 4.72300+05 4.00000+02          0          0         12          0 144 8457    9
 3.00000+00 0.00000+00 9.94975+01 4.99987-01 0.00000+00 0.00000+00 144 8457   10
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 144 8457   11
 0.00000+00 1.00000+00          0          0          6          1 144 8457   12
 1.00000-02 0.00000+00 1.38435+04 1.38435+04 0.00000+00 0.00000+00 144 8457   13
 5.98662+06 7.20932+02          0          0          6          0 144 8457   14
 1.00000+00 1.00000+00 5.00000-01 5.00000-01 0.00000+00 0.00000+00 144 8457   15
                                                                   144 8  099999
                                                                   144 0  0    0
                                                                     0 0  0    0
 1.102500+4 2.477530+1         -1          0          2          1 145 1451    1
 0.000000+0 1.000000+0          0          0          0          6 145 1451    2
 0.000000+0 0.000000+0          0          0          4        311 145 1451    3
 0.000000+0 0.000000+0          0          0         37          2 145 1451    4
 11-Na- 25 HAR+WIN    EVAL-OCT82 A.L. NICHOLS                      145 1451    5
                      DIST-NOV07                       261107      145 1451    6
----JEFF-311          MATERIAL  145                                145 1451    7
-----RADIOACTIVE DECAY DATA                                        145 1451    8
------ENDF-6 FORMAT                                                145 1451    9
****************************************************************** 145 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 145 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 145 1451   12
**             Original data taken from:  UKPADD67              ** 145 1451   13
****************************************************************** 145 1451   14
      P.M.ENDT, C.VAN DER LEUN     NUCL PHYS   A105(1967)1         145 1451   15
      P.M.ENDT, C.VAN DER LEUN     NUCL PHYS   A214(1973)1         145 1451   16
      P.M.ENDT, C.VAN DER LEUN     NUCL PHYS   A310(1978)1         145 1451   17
      A.D.W.JONES ET AL            PHYS REV      C1(1970)1000      145 1451   18
      D.E.ALBURGER, D.H.WILKINSON  PHYS REV      C3(1971)1957      145 1451   19
                                                                   145 1451   20
          BETA DATA HAVE BEEN CALCULATED FROM THE GAMMA INTENSITY  145 1451   21
      DATA REPORTED BY ALBURGER AND WILKINSON.                     145 1451   22
                                                                   145 1451   23
                                                                   145 1451   24
      MEAN BETA- ENERGIES:-                                        145 1451   25
   END POINT(MEV)= 1.0320  SHAPE= 0  MEAN= 0.3946  INT= 0.0027     145 1451   26
   END POINT(MEV)= 1.8680  SHAPE= 0  MEAN= 0.7730  INT= 0.0046     145 1451   27
   END POINT(MEV)= 2.2210  SHAPE= 0  MEAN= 0.9385  INT= 0.0950     145 1451   28
   END POINT(MEV)= 2.8580  SHAPE= 0  MEAN= 1.2416  INT= 0.2720     145 1451   29
   END POINT(MEV)= 3.8330  SHAPE= 0  MEAN= 1.7127  INT= 0.6250     145 1451   30
                                                                   145 1451   31
      MEAN GAMMA ENERGY              =    431.4846  KEV            145 1451   32
      MEAN BETA- ENERGY              =   1496.4905  KEV            145 1451   33
      BETA- + NEUTRINO ENERGY        =   3395.3752  KEV            145 1451   34
      INTERNAL BREMSSTRAHLUNG ENERGY =      5.4159  KEV            145 1451   35
      EFFECTIVE Q VALUE              =   3833.0000  KEV            145 1451   36
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.1826                 145 1451   37
      CALCULATED Q VALUE             =   3826.8601  KEV            145 1451   38
      % DEVIATION                    =      0.1602                 145 1451   39
                                                                   145 1451   40
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).          145 1451   41
                                1        451         43          1 145 1451   42
                                8        457         49          1 145 1451   43
 0.000000+0 0.000000+0          0          0          0          0 145 1  099999
                                                                   145 0  0    0
1.10250E+042.47753E+01          0          0          0          2 145 8457    1
5.96000E+017.00000E-01          0          0          6          0 145 8457    2
1.49649E+063.71858E+044.36900E+051.19004E+040.00000E+000.00000E+00 145 8457    3
2.50000E+00 1.0000E+00          0          0          6          1 145 8457    4
1.00000E+000.00000E+003.83300E+067.00000E+031.00000E+000.00000E+00 145 8457    5
0.00000E+000.00000E+00          0          0          6         10 145 8457    6
1.45000E-010.00000E+004.31485E+051.18881E+040.00000E+000.00000E+00 145 8457    7
3.89700E+051.00000E+02          0          0         12          0 145 8457    8
1.00000E+000.00000E+008.89655E-013.44828E-020.00000E+000.00000E+00 145 8457    9
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   10
5.85100E+051.00000E+02          0          0         12          0 145 8457   11
1.00000E+000.00000E+008.68966E-013.44828E-020.00000E+000.00000E+00 145 8457   12
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   13
8.36000E+051.00000E+03          0          0         12          0 145 8457   14
1.00000E+000.00000E+007.58621E-032.06897E-030.00000E+000.00000E+00 145 8457   15
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   16
9.74800E+051.00000E+02          0          0         12          0 145 8457   17
1.00000E+000.00000E+001.00000E+004.13793E-020.00000E+000.00000E+00 145 8457   18
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   19
9.90000E+051.00000E+03          0          0         12          0 145 8457   20
1.00000E+000.00000E+001.03448E-022.06897E-030.00000E+000.00000E+00 145 8457   21
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   22
1.38000E+061.00000E+03          0          0         12          0 145 8457   23
1.00000E+000.00000E+001.79310E-023.44828E-030.00000E+000.00000E+00 145 8457   24
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   25
1.61170E+061.00000E+02          0          0         12          0 145 8457   26
1.00000E+000.00000E+006.55172E-014.13793E-020.00000E+000.00000E+00 145 8457   27
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   28
1.96500E+061.00000E+03          0          0         12          0 145 8457   29
1.00000E+000.00000E+001.10345E-022.06897E-030.00000E+000.00000E+00 145 8457   30
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   31
2.21600E+061.00000E+03          0          0         12          0 145 8457   32
1.00000E+000.00000E+006.89655E-031.37931E-030.00000E+000.00000E+00 145 8457   33
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   34
2.80090E+065.00000E+02          0          0         12          0 145 8457   35
1.00000E+000.00000E+004.13793E-036.89655E-040.00000E+000.00000E+00 145 8457   36
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 145 8457   37
0.00000E+001.00000E+00          0          0          6          5 145 8457   38
1.00000E+000.00000E+001.49649E+063.71858E+040.00000E+000.00000E+00 145 8457   39
1.03200E+068.00000E+03          0          0          6          0 145 8457   40
1.00000E+001.00000E+002.70000E-036.00000E-040.00000E+000.00000E+00 145 8457   41
1.86800E+068.00000E+03          0          0          6          0 145 8457   42
1.00000E+001.00000E+004.60000E-035.00000E-040.00000E+000.00000E+00 145 8457   43
2.22100E+067.00000E+03          0          0          6          0 145 8457   44
1.00000E+001.00000E+009.50000E-026.00000E-030.00000E+000.00000E+00 145 8457   45
2.85800E+067.00000E+03          0          0          6          0 145 8457   46
1.00000E+001.00000E+002.72000E-011.10000E-020.00000E+000.00000E+00 145 8457   47
3.83300E+067.00000E+03          0          0          6          0 145 8457   48
1.00000E+001.00000E+006.25000E-012.00000E-020.00000E+000.00000E+00 145 8457   49
                                                                   145 8  099999
                                                                   145 0  0    0
                                                                     0 0  0    0
 1.102600+4 2.576930+1         -1          0          2          1 146 1451    1
 0.000000+0 1.000000+0          0          0          0          6 146 1451    2
 0.000000+0 0.000000+0          0          0          4        311 146 1451    3
 0.000000+0 0.000000+0          0          0         47          2 146 1451    4
 11-Na- 26 HAR+WIN    EVAL-NOV82 A.L. NICHOLS                      146 1451    5
                      DIST-NOV07                       261107      146 1451    6
----JEFF-311          MATERIAL  146                                146 1451    7
-----RADIOACTIVE DECAY DATA                                        146 1451    8
------ENDF-6 FORMAT                                                146 1451    9
****************************************************************** 146 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 146 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 146 1451   12
**             Original data taken from:  UKPADD67              ** 146 1451   13
****************************************************************** 146 1451   14
      P.M.ENDT, C.VAN DER LEUN     NUCL PHYS   A310(1978)1         146 1451   15
      M.J.NURMIA, R.W.FINK         NUCL PHYS      8(1958)139       146 1451   16
      E.L.ROBINSON ET AL           PHYS REV     122(1961)202       146 1451   17
      R.KLAPISCH ET AL             PHYS REV LETT 29(1972)1254      146 1451   18
      G.KLOTZ ET AL                NUCL PHYS   A205(1973)90        146 1451   19
      D.E.ALBURGER ET AL           PHYS REV      C8(1973)1011      146 1451   20
                                                                   146 1451   21
          THE BETA AND GAMMA DECAY DATA HAVE BEEN DERIVED FROM THE 146 1451   22
      MEASUREMENTS OF KLOTZ ET AL AND ALBURGER ET AL.  GAMMA       146 1451   23
      TRANSITION PROBABILITIES WERE CALCULATED IN CONJUNCTION WITH 146 1451   24
      THE BRANCHING FRACTIONS LISTED BY ENDT AND VAN DER LEUN.     146 1451   25
      THIS RESULTS IN SOME DISAGREEMENT BETWEEN THE CALCULATED     146 1451   26
      INTENSITY DATA AND THE MEASURED DATA OF ALBURGER ET AL FOR   146 1451   27
      THE 1002 AND 1412 GAMMA EMISSIONS.                           146 1451   28
                                                                   146 1451   29
                                                                   146 1451   30
      MEAN BETA- ENERGIES:-                                        146 1451   31
   END POINT(MEV)= 3.2000  SHAPE= 0  MEAN= 1.4061  INT= 0.0170     146 1451   32
   END POINT(MEV)= 3.6100  SHAPE= 0  MEAN= 1.6044  INT= 0.0070     146 1451   33
   END POINT(MEV)= 4.4250  SHAPE= 0  MEAN= 2.0010  INT= 0.0030     146 1451   34
   END POINT(MEV)= 4.4910  SHAPE= 0  MEAN= 2.0333  INT= 0.0270     146 1451   35
   END POINT(MEV)= 4.9750  SHAPE= 0  MEAN= 2.2700  INT= 0.0270     146 1451   36
   END POINT(MEV)= 4.9930  SHAPE= 0  MEAN= 2.2788  INT= 0.0200     146 1451   37
   END POINT(MEV)= 5.0070  SHAPE= 0  MEAN= 2.2857  INT= 0.0050     146 1451   38
   END POINT(MEV)= 5.3850  SHAPE= 0  MEAN= 2.4710  INT= 0.0150     146 1451   39
   END POINT(MEV)= 7.5160  SHAPE= 0  MEAN= 3.5192  INT= 0.8790     146 1451   40
                                                                   146 1451   41
      MEAN GAMMA ENERGY              =   2164.9612  KEV            146 1451   42
      MEAN BETA- ENERGY              =   3329.4490  KEV            146 1451   43
      BETA- + NEUTRINO ENERGY        =   7160.7612  KEV            146 1451   44
      INTERNAL BREMSSTRAHLUNG ENERGY =     15.3281  KEV            146 1451   45
      EFFECTIVE Q VALUE              =   9325.0000  KEV            146 1451   46
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.2466                 146 1451   47
      CALCULATED Q VALUE             =   9325.7217  KEV            146 1451   48
      % DEVIATION                    =     -0.0077                 146 1451   49
                                                                   146 1451   50
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).          146 1451   51
                                1        451         53          1 146 1451   52
                                8        457         84          1 146 1451   53
 0.000000+0 0.000000+0          0          0          0          0 146 1  099999
                                                                   146 0  0    0
1.10260E+042.57693E+01          0          0          0          2 146 8457    1
1.08000E+001.00000E-02          0          0          6          0 146 8457    2
3.32945E+062.10588E+042.18029E+063.88609E+040.00000E+000.00000E+00 146 8457    3
3.00000E+00 1.0000E+00          0          0          6          1 146 8457    4
1.00000E+000.00000E+009.32500E+062.30000E+041.00000E+000.00000E+00 146 8457    5
0.00000E+000.00000E+00          0          0          6         19 146 8457    6
9.90000E-010.00000E+002.16496E+063.88306E+040.00000E+000.00000E+00 146 8457    7
1.00200E+061.00000E+03          0          0         12          0 146 8457    8
1.00000E+000.00000E+001.21212E-022.02020E-030.00000E+000.00000E+00 146 8457    9
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   10
1.12970E+062.00000E+02          0          0         12          0 146 8457   11
1.00000E+000.00000E+005.25253E-026.06061E-030.00000E+000.00000E+00 146 8457   12
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   13
1.36570E+067.00000E+02          0          0         12          0 146 8457   14
1.00000E+000.00000E+002.62626E-034.04040E-040.00000E+000.00000E+00 146 8457   15
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   16
1.39350E+065.00000E+02          0          0         12          0 146 8457   17
1.00000E+000.00000E+002.02020E-032.02020E-040.00000E+000.00000E+00 146 8457   18
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   19
1.41200E+061.00000E+03          0          0         12          0 146 8457   20
1.00000E+000.00000E+002.02020E-022.02020E-030.00000E+000.00000E+00 146 8457   21
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   22
1.77500E+062.00000E+03          0          0         12          0 146 8457   23
1.00000E+000.00000E+001.81818E-022.02020E-030.00000E+000.00000E+00 146 8457   24
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   25
1.80870E+061.00000E+02          0          0         12          0 146 8457   26
1.00000E+000.00000E+001.00000E+002.02020E-020.00000E+000.00000E+00 146 8457   27
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   28
1.89600E+061.00000E+03          0          0         12          0 146 8457   29
1.00000E+000.00000E+002.22222E-022.02020E-030.00000E+000.00000E+00 146 8457   30
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   31
2.13200E+061.00000E+03          0          0         12          0 146 8457   32
1.00000E+000.00000E+007.47475E-031.01010E-030.00000E+000.00000E+00 146 8457   33
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   34
2.18500E+062.00000E+03          0          0         12          0 146 8457   35
1.00000E+000.00000E+001.71717E-032.02020E-040.00000E+000.00000E+00 146 8457   36
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   37
2.50970E+066.00000E+02          0          0         12          0 146 8457   38
1.00000E+000.00000E+005.05051E-031.01010E-030.00000E+000.00000E+00 146 8457   39
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   40
2.52320E+065.00000E+02          0          0         12          0 146 8457   41
1.00000E+000.00000E+001.61616E-022.02020E-030.00000E+000.00000E+00 146 8457   42
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   43
2.54100E+061.00000E+03          0          0         12          0 146 8457   44
1.00000E+000.00000E+002.52525E-023.03030E-030.00000E+000.00000E+00 146 8457   45
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   46
2.77700E+061.00000E+03          0          0         12          0 146 8457   47
1.00000E+000.00000E+001.81818E-033.03030E-040.00000E+000.00000E+00 146 8457   48
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   49
2.93840E+061.00000E+02          0          0         12          0 146 8457   50
1.00000E+000.00000E+005.85859E-037.07071E-040.00000E+000.00000E+00 146 8457   51
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   52
3.02560E+065.00000E+02          0          0         12          0 146 8457   53
1.00000E+000.00000E+001.41414E-032.02020E-040.00000E+000.00000E+00 146 8457   54
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   55
3.09200E+061.00000E+03          0          0         12          0 146 8457   56
1.00000E+000.00000E+003.03030E-031.01010E-030.00000E+000.00000E+00 146 8457   57
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   58
4.33190E+064.00000E+02          0          0         12          0 146 8457   59
1.00000E+000.00000E+001.61616E-032.02020E-040.00000E+000.00000E+00 146 8457   60
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   61
4.83430E+064.00000E+02          0          0         12          0 146 8457   62
1.00000E+000.00000E+003.53535E-034.04040E-040.00000E+000.00000E+00 146 8457   63
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+00 146 8457   64
0.00000E+001.00000E+00          0          0          6          9 146 8457   65
1.00000E+000.00000E+003.32945E+062.10588E+040.00000E+000.00000E+00 146 8457   66
3.20000E+062.50000E+04          0          0          6          0 146 8457   67
1.00000E+001.00000E+001.70000E-022.00000E-030.00000E+000.00000E+00 146 8457   68
3.61000E+062.40000E+04          0          0          6          0 146 8457   69
1.00000E+001.00000E+007.00000E-031.00000E-030.00000E+000.00000E+00 146 8457   70
4.42500E+062.40000E+04          0          0          6          0 146 8457   71
1.00000E+001.00000E+003.00000E-031.00000E-030.00000E+000.00000E+00 146 8457   72
4.49100E+062.40000E+04          0          0          6          0 146 8457   73
1.00000E+001.00000E+002.70000E-023.00000E-030.00000E+000.00000E+00 146 8457   74
4.97500E+062.30000E+04          0          0          6          0 146 8457   75
1.00000E+001.00000E+002.70000E-023.00000E-030.00000E+000.00000E+00 146 8457   76
4.99300E+062.40000E+04          0          0          6          0 146 8457   77
1.00000E+001.00000E+002.00000E-022.00000E-030.00000E+000.00000E+00 146 8457   78
5.00700E+062.40000E+04          0          0          6          0 146 8457   79
1.00000E+001.00000E+005.00000E-031.00000E-030.00000E+000.00000E+00 146 8457   80
5.38500E+062.30000E+04          0          0          6          0 146 8457   81
1.00000E+001.00000E+001.50000E-022.00000E-030.00000E+000.00000E+00 146 8457   82
7.51600E+062.30000E+04          0          0          6          0 146 8457   83
1.00000E+001.00000E+008.79000E-014.00000E-030.00000E+000.00000E+00 146 8457   84
                                                                   146 8  099999
                                                                   146 0  0    0
                                                                     0 0  0    0
 1.102700+4 2.676220+1         -1          0          2          1 147 1451    1
 0.000000+0 1.000000+0          0          0          0          6 147 1451    2
 0.000000+0 0.000000+0          0          0          4        311 147 1451    3
 0.000000+0 0.000000+0          0          0         53          2 147 1451    4
 11-Na- 27 ENSDF      EVAL-MAR01 CONVERSION OF ENSDF               147 1451    5
 /ENSDF/              DIST-NOV07                       261107      147 1451    6
----JEFF-311          MATERIAL  147                                147 1451    7
-----RADIOACTIVE DECAY DATA                                        147 1451    8
------ENDF-6 FORMAT                                                147 1451    9
****************************************************************** 147 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 147 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 147 1451   12
**             Original data taken from:  ENSDF                 ** 147 1451   13
****************************************************************** 147 1451   14
****************************************************************** 147 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 147 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 147 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 147 1451   18
****************************************************************** 147 1451   19
27NA  DECAY 301 MS    6                     I(min) = 0.0E+00 %     147 1451   20
         Ex = 0.0         keV                     1 decay mode(s)  147 1451   21
                                                                   147 1451   22
27NA B- DECAY               Q =  9010.0000 keV      40.0000        147 1451   23
         Branching                100.0000 %         0.0000        147 1451   24
                         Br*Q =  9010.0000 keV      40.0000        147 1451   25
                                              0 isomeric state(s)  147 1451   26
                                                                   147 1451   27
Individual beta- transitions                                       147 1451   28
Final level    end point    shape    av.energy        intensity    147 1451   29
 4992.300   4016.251  39.996  0   1769.000  20.000    0.250 0.000  147 1451   30
 4776.100   4232.373  39.994  0   1875.000  20.000    0.220 0.000  147 1451   31
 4552.800   4455.592  39.990  0   1984.000  20.000    0.330 0.000  147 1451   32
 4149.800   4858.447  39.988  0   2181.000  20.000    0.065 0.000  147 1451   33
 3490.700   5517.309  39.992  0   2504.000  20.000    0.560 0.000  147 1451   34
 3426.900   5581.086  39.989  0   2536.000  20.000    0.800 0.000  147 1451   35
 3109.400   5898.472  39.986  0   2692.000  20.000    0.600 0.000  147 1451   36
 1940.000   7067.450  39.986  0   3268.000  20.000    0.500 0.000  147 1451   37
 1698.000   7309.363  39.986  0   3387.000  20.000   11.200 0.000  147 1451   38
  984.660   8022.445  39.986  0   3740.000  20.000   84.300 0.000  147 1451   39
                                                                   147 1451   40
         Mean alpha    energy       0.0000 keV       0.0000        147 1451   41
         Mean beta     energy    3615.4788 keV      17.0103        147 1451   42
         Mean conv. e- energy       0.0000 keV       0.0000        147 1451   43
         Mean Auger e- energy       0.0000 keV       0.0000        147 1451   44
         Mean gamma    energy    1166.3045 keV                     147 1451   45
         Mean X        energy       0.0000 keV       0.0000        147 1451   46
         Mean recoil   energy       2.8018 keV       0.0123        147 1451   47
         Mean neutrino energy    4149.5782 keV      17.0103        147 1451   48
         Mean neutron  energy       0.0000 keV       0.0000        147 1451   49
         Total         energy    8934.1922 keV      49.2116        147 1451   50
         Q effective             9010.0000 keV      40.0000        147 1451   51
         diff. mode               -75.8078 keV      -0.8414 %      147 1451   52
                                                                   147 1451   53
         Mean e- bind. energy       0.0000 keV                     147 1451   54
         diff. atomic               0.0000 keV       0.0000 %      147 1451   55
         diff. nuclear            -75.8078 keV      -0.8414 %      147 1451   56
                                                                   147 1451   57
                                1        451         59          0 147 1451   58
                                8        457         80          0 147 1451   59
 0.000000+0 0.000000+0          0          0          0          0 147 1  099999
                                                                   147 0  0    0
 1.10270+04 2.67622+01          0          0          0          2 147 8457    1
 3.01000-01 6.00000-03          0          0          6          0 147 8457    2
 3.61548+06 1.70103+04 1.16630+06 4.29312+04 2.80184+03 1.22711+01 147 8457    3
 2.50000+00 1.00000+00          0          0          6          1 147 8457    4
 1.00000+00 0.00000+00 9.01000+06 4.00000+04 1.00000+00 0.00000+00 147 8457    5
 0.00000+00 0.00000+00          0          0          6         17 147 8457    6
 1.00000-02 0.00000+00 1.16630+06 4.29312+04 0.00000+00 0.00000+00 147 8457    7
 7.13300+05 0.00000+00          0          0         12          0 147 8457    8
 1.00000+00 0.00000+00 4.35000-01 4.35000-01 0.00000+00 0.00000+00 147 8457    9
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   10
 9.55300+05 1.00000+02          0          0         12          0 147 8457   11
 1.00000+00 0.00000+00 8.70000-01 8.70000-01 0.00000+00 0.00000+00 147 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   13
 9.84660+05 8.00000+01          0          0         12          0 147 8457   14
 1.00000+00 0.00000+00 8.70000+01 0.00000+00 0.00000+00 0.00000+00 147 8457   15
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   16
 1.16940+06 2.00000+02          0          0         12          0 147 8457   17
 1.00000+00 0.00000+00 5.91600-01 6.09000-02 0.00000+00 0.00000+00 147 8457   18
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   19
 1.48690+06 5.00000+02          0          0         12          0 147 8457   20
 1.00000+00 0.00000+00 4.17600-01 6.09000-02 0.00000+00 0.00000+00 147 8457   21
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   22
 1.66660+06 8.00000+02          0          0         12          0 147 8457   23
 1.00000+00 0.00000+00 9.57000-02 3.48000-02 0.00000+00 0.00000+00 147 8457   24
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   25
 1.69790+06 1.00000+02          0          0         12          0 147 8457   26
 1.00000+00 0.00000+00 1.18320+01 6.09000-01 0.00000+00 0.00000+00 147 8457   27
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   28
 1.72880+06 1.00000+02          0          0         12          0 147 8457   29
 1.00000+00 0.00000+00 3.21900-01 4.35000-02 0.00000+00 0.00000+00 147 8457   30
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   31
 1.79260+06 7.00000+02          0          0         12          0 147 8457   32
 1.00000+00 0.00000+00 1.47900-01 3.48000-02 0.00000+00 0.00000+00 147 8457   33
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   34
 1.93990+06 1.00000+02          0          0         12          0 147 8457   35
 1.00000+00 0.00000+00 4.61100-01 5.22000-02 0.00000+00 0.00000+00 147 8457   36
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   37
 2.45170+06 4.00000+02          0          0         12          0 147 8457   38
 1.00000+00 0.00000+00 2.61000-02 8.70000-03 0.00000+00 0.00000+00 147 8457   39
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   40
 2.50590+06 7.00000+02          0          0         12          0 147 8457   41
 1.00000+00 0.00000+00 2.52300-01 4.35000-02 0.00000+00 0.00000+00 147 8457   42
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   43
 2.61270+06 6.00000+02          0          0         12          0 147 8457   44
 1.00000+00 0.00000+00 1.74000-01 5.22000-02 0.00000+00 0.00000+00 147 8457   45
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   46
 2.83590+06 8.00000+02          0          0         12          0 147 8457   47
 1.00000+00 0.00000+00 6.35100-02 1.30500-02 0.00000+00 0.00000+00 147 8457   48
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   49
 3.10920+06 2.00000+02          0          0         12          0 147 8457   50
 1.00000+00 0.00000+00 1.30500+00 1.30500+00 0.00000+00 0.00000+00 147 8457   51
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   52
 3.49050+06 7.00000+02          0          0         12          0 147 8457   53
 1.00000+00 0.00000+00 1.21800-01 4.35000-02 0.00000+00 0.00000+00 147 8457   54
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   55
 4.00730+06 9.00000+02          0          0         12          0 147 8457   56
 1.00000+00 0.00000+00 1.82700-01 3.48000-02 0.00000+00 0.00000+00 147 8457   57
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 147 8457   58
 0.00000+00 1.00000+00          0          0          6         10 147 8457   59
 1.00000-02 0.00000+00 3.61548+06 1.70103+04 0.00000+00 0.00000+00 147 8457   60
 4.01625+06 3.99957+04          0          0          6          0 147 8457   61
 1.00000+00 1.00000+00 2.50000-01 0.00000+00 0.00000+00 0.00000+00 147 8457   62
 4.23237+06 3.99936+04          0          0          6          0 147 8457   63
 1.00000+00 1.00000+00 2.20000-01 0.00000+00 0.00000+00 0.00000+00 147 8457   64
 4.45559+06 3.99901+04          0          0          6          0 147 8457   65
 1.00000+00 1.00000+00 3.30000-01 0.00000+00 0.00000+00 0.00000+00 147 8457   66
 4.85845+06 3.99876+04          0          0          6          0 147 8457   67
 1.00000+00 1.00000+00 6.50000-02 0.00000+00 0.00000+00 0.00000+00 147 8457   68
 5.51731+06 3.99917+04          0          0          6          0 147 8457   69
 1.00000+00 1.00000+00 5.60000-01 0.00000+00 0.00000+00 0.00000+00 147 8457   70
 5.58109+06 3.99887+04          0          0          6          0 147 8457   71
 1.00000+00 1.00000+00 8.00000-01 0.00000+00 0.00000+00 0.00000+00 147 8457   72
 5.89847+06 3.99861+04          0          0          6          0 147 8457   73
 1.00000+00 1.00000+00 6.00000-01 0.00000+00 0.00000+00 0.00000+00 147 8457   74
 7.06745+06 3.99857+04          0          0          6          0 147 8457   75
 1.00000+00 1.00000+00 5.00000-01 0.00000+00 0.00000+00 0.00000+00 147 8457   76
 7.30936+06 3.99857+04          0          0          6          0 147 8457   77
 1.00000+00 1.00000+00 1.12000+01 0.00000+00 0.00000+00 0.00000+00 147 8457   78
 8.02245+06 3.99857+04          0          0          6          0 147 8457   79
 1.00000+00 1.00000+00 8.43000+01 0.00000+00 0.00000+00 0.00000+00 147 8457   80
                                                                   147 8  099999
                                                                   147 0  0    0
                                                                     0 0  0    0
 1.102800+4 2.775840+1         -1          0          2          1 148 1451    1
 0.000000+0 1.000000+0          0          0          0          6 148 1451    2
 0.000000+0 0.000000+0          0          0          4        311 148 1451    3
 0.000000+0 0.000000+0          0          0         49          2 148 1451    4
 11-Na- 28 ENSDF      EVAL-MAR01 CONVERSION OF ENSDF               148 1451    5
 /ENSDF/              DIST-NOV07                       261107      148 1451    6
----JEFF-311          MATERIAL  148                                148 1451    7
-----RADIOACTIVE DECAY DATA                                        148 1451    8
------ENDF-6 FORMAT                                                148 1451    9
****************************************************************** 148 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 148 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 148 1451   12
**             Original data taken from:  ENSDF                 ** 148 1451   13
****************************************************************** 148 1451   14
****************************************************************** 148 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  * 148 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          * 148 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              * 148 1451   18
****************************************************************** 148 1451   19
28NA  DECAY 30.5 MS   4                     I(min) = 0.0E+00 %     148 1451   20
         Ex = 0.0         keV                     1 decay mode(s)  148 1451   21
                                                                   148 1451   22
28NA B- DECAY               Q = 13880.0000 keV     110.0000        148 1451   23
         Branching                100.0000 %         0.0000        148 1451   24
                         Br*Q = 13880.0000 keV     110.0000        148 1451   25
                                              0 isomeric state(s)  148 1451   26
                                                                   148 1451   27
Individual beta- transitions                                       148 1451   28
Final level    end point    shape    av.energy        intensity    148 1451   29
 5271.700   8603.669 109.945  0   4062.000  55.000    0.500 0.150  148 1451   30
 4560.800   9314.187 109.943  0   4413.000  55.000    2.600 0.500  148 1451   31
 4557.000   9317.985 109.942  0   4415.000  55.000    1.300 0.300  148 1451   32
 3862.700  10011.911 109.942  0   4758.000  55.000   19.000 3.000  148 1451   33
 1473.400  12399.926 109.942  0   5940.000  55.000   14.000 6.000  148 1451   34
    0.000  13872.534 109.941  0   6668.000  55.000   63.000 6.000  148 1451   35
                                                                   148 1451   36
         Mean alpha    energy       0.0000 keV       0.0000        148 1451   37
         Mean beta     energy    6128.9030 keV     556.3550        148 1451   38
         Mean conv. e- energy       0.0000 keV       0.0000        148 1451   39
         Mean Auger e- energy       0.0000 keV       0.0000        148 1451   40
         Mean gamma    energy    1138.6535 keV                     148 1451   41
         Mean X        energy       0.0000 keV       0.0000        148 1451   42
         Mean recoil   energy       6.8807 keV       0.6242        148 1451   43
         Mean neutrino energy    6655.3670 keV     603.4631        148 1451   44
         Mean neutron  energy       0.0000 keV       0.0000        148 1451   45
         Total         energy   13929.8499 keV     826.4867        148 1451   46
         Q effective            13880.0000 keV     110.0000        148 1451   47
         diff. mode                49.8499 keV       0.3591 %      148 1451   48
                                                                   148 1451   49
         Mean e- bind. energy       0.0000 keV                     148 1451   50
         diff. atomic               0.0000 keV       0.0000 %      148 1451   51
         diff. nuclear             49.8499 keV       0.3591 %      148 1451   52
                                                                   148 1451   53
                                1        451         55          0 148 1451   54
                                8        457         36          0 148 1451   55
 0.000000+0 0.000000+0          0          0          0          0 148 1  099999
                                                                   148 0  0    0
 1.10280+04 2.77584+01          0          0          0          2 148 8457    1
 3.05000-02 4.00000-04          0          0          6          0 148 8457    2
 6.12890+06 5.56355+05 1.13865+06 9.68577+04 6.88071+03 6.24228+02 148 8457    3
 1.00000+00 1.00000+00          0          0          6          1 148 8457    4
 1.00000+00 0.00000+00 1.38800+07 1.10000+05 1.00000+00 0.00000+00 148 8457    5
 0.00000+00 0.00000+00          0          0          6          5 148 8457    6
 1.00000-02 0.00000+00 1.13865+06 9.68577+04 0.00000+00 0.00000+00 148 8457    7
 1.47340+06 6.00000+02          0          0         12          0 148 8457    8
 1.00000+00 0.00000+00 3.70000+01 5.00000+00 0.00000+00 0.00000+00 148 8457    9
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 148 8457   10
 2.38920+06 8.00000+02          0          0         12          0 148 8457   11
 1.00000+00 0.00000+00 1.87000+01 2.50000+00 0.00000+00 0.00000+00 148 8457   12
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 148 8457   13
 3.08340+06 8.00000+02          0          0         12          0 148 8457   14
 1.00000+00 0.00000+00 1.30000+00 3.00000-01 0.00000+00 0.00000+00 148 8457   15
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 148 8457   16
 3.08740+06 7.00000+02          0          0         12          0 148 8457   17
 1.00000+00 0.00000+00 2.60000+00 5.00000-01 0.00000+00 0.00000+00 148 8457   18
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 148 8457   19
 5.27170+06 8.00000+02          0          0         12          0 148 8457   20
 1.00000+00 0.00000+00 5.00000-01 1.50000-01 0.00000+00 0.00000+00 148 8457   21
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 148 8457   22
 0.00000+00 1.00000+00          0          0          6          6 148 8457   23
 1.00000-02 0.00000+00 6.12890+06 5.56355+05 0.00000+00 0.00000+00 148 8457   24
 8.60367+06 1.09945+05          0          0          6          0 148 8457   25
 1.00000+00 1.00000+00 5.00000-01 1.50000-01 0.00000+00 0.00000+00 148 8457   26
 9.31419+06 1.09943+05          0          0          6          0 148 8457   27
 1.00000+00 1.00000+00 2.60000+00 5.00000-01 0.00000+00 0.00000+00 148 8457   28
 9.31798+06 1.09942+05          0          0          6          0 148 8457   29
 1.00000+00 1.00000+00 1.30000+00 3.00000-01 0.00000+00 0.00000+00 148 8457   30
 1.00119+07 1.09942+05          0          0          6          0 148 8457   31
 1.00000+00 1.00000+00 1.90000+01 3.00000+00 0.00000+00 0.00000+00 148 8457   32
 1.23999+07 1.09942+05          0          0          6          0 148 8457   33
 1.00000+00 1.00000+00 1.40000+01 6.00000+00 0.00000+00 0.00000+00 148 8457   34
 1.38725+07 1.09941+05          0          0          6          0 148 8457   35
 1.00000+00 1.00000+00 6.30000+01 6.00000+00 0.00000+00 0.00000+00 148 8457   36
                                                                   148 8  099999
                                                                   148 0  0    0
                                                                     0 0  0    0
 1.102900+4 2.875370+1         -1          0          2          1 149 1451    1
 0.000000+0 1.000000+0          0          0          0          6 149 1451    2
 0.000000+0 0.000000+0          0          0          4        311 149 1451    3
 0.000000+0 0.000000+0          0          0         18          2 149 1451    4
 11-Na- 29 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  149 1451    5
                      DIST-NOV07                       261107      149 1451    6
----JEFF-311          MATERIAL  149                                149 1451    7
-----RADIOACTIVE DECAY DATA                                        149 1451    8
------ENDF-6 FORMAT                                                149 1451    9
****************************************************************** 149 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 149 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 149 1451   12
**             Original data taken from:  NUBASE                ** 149 1451   13
****************************************************************** 149 1451   14
****************************************************************** 149 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 149 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      149 1451   17
                                                                   149 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           149 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        149 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               149 1451   21
****************************************************************** 149 1451   22
                                1        451         24          0 149 1451   23
                                8        457          6          0 149 1451   24
 0.000000+0 0.000000+0          0          0          0          0 149 1  099999
                                                                   149 0  0    0
 1.10290+04 2.87537+01          0          0          0          0 149 8457    1
 4.49000-02 1.20000-03          0          0          6          0 149 8457    2
 3.90354+06 0.00000+00 3.90354+06 0.00000+00 6.22396+05 0.00000+00 149 8457    3
 1.50000+00 1.00000+00          0          0         12          2 149 8457    4
 1.00000+00 0.00000+00 1.32840+07 0.00000+00 7.41000-01 0.00000+00 149 8457    5
 1.50000+00 0.00000+00 9.61230+06 0.00000+00 2.59000-01 0.00000+00 149 8457    6
                                                                   149 8  099999
                                                                   149 0  0    0
                                                                     0 0  0    0
 1.103000+4 2.975120+1         -1          0          2          1 150 1451    1
 0.000000+0 1.000000+0          0          0          0          6 150 1451    2
 0.000000+0 0.000000+0          0          0          4        311 150 1451    3
 0.000000+0 0.000000+0          0          0         18          2 150 1451    4
 11-Na- 30 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  150 1451    5
                      DIST-NOV07                       261107      150 1451    6
----JEFF-311          MATERIAL  150                                150 1451    7
-----RADIOACTIVE DECAY DATA                                        150 1451    8
------ENDF-6 FORMAT                                                150 1451    9
****************************************************************** 150 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 150 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 150 1451   12
**             Original data taken from:  NUBASE                ** 150 1451   13
****************************************************************** 150 1451   14
****************************************************************** 150 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 150 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      150 1451   17
                                                                   150 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           150 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        150 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               150 1451   21
****************************************************************** 150 1451   22
                                1        451         24          0 150 1451   23
                                8        457          8          0 150 1451   24
 0.000000+0 0.000000+0          0          0          0          0 150 1  099999
                                                                   150 0  0    0
 1.10300+04 2.97512+01          0          0          0          0 150 8457    1
 4.84000-02 1.70000-03          0          0          6          0 150 8457    2
 4.80209+06 0.00000+00 4.80209+06 0.00000+00 8.39321+05 0.00000+00 150 8457    3
 2.00000+00 1.00000+00          0          0         24          4 150 8457    4
 1.00000+00 0.00000+00 1.72720+07 0.00000+00 6.88299-01 0.00000+00 150 8457    5
 1.50000+00 0.00000+00 1.09087+07 0.00000+00 3.00000-01 0.00000+00 150 8457    6
 1.55000+00 0.00000+00 7.23700+06 0.00000+00 1.17000-02 0.00000+00 150 8457    7
 1.40000+00 0.00000+00 5.50610+06 0.00000+00 5.50000-07 0.00000+00 150 8457    8
                                                                   150 8  099999
                                                                   150 0  0    0
                                                                     0 0  0    0
 1.103100+4 3.074720+1         -1          0          2          1 151 1451    1
 0.000000+0 1.000000+0          0          0          0          6 151 1451    2
 0.000000+0 0.000000+0          0          0          4        311 151 1451    3
 0.000000+0 0.000000+0          0          0         18          2 151 1451    4
 11-Na- 31 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  151 1451    5
                      DIST-NOV07                       261107      151 1451    6
----JEFF-311          MATERIAL  151                                151 1451    7
-----RADIOACTIVE DECAY DATA                                        151 1451    8
------ENDF-6 FORMAT                                                151 1451    9
****************************************************************** 151 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 151 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 151 1451   12
**             Original data taken from:  NUBASE                ** 151 1451   13
****************************************************************** 151 1451   14
****************************************************************** 151 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 151 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      151 1451   17
                                                                   151 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           151 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        151 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               151 1451   21
****************************************************************** 151 1451   22
                                1        451         24          0 151 1451   23
                                8        457          8          0 151 1451   24
 0.000000+0 0.000000+0          0          0          0          0 151 1  099999
                                                                   151 0  0    0
 1.10310+04 3.07472+01          0          0          0          0 151 8457    1
 1.70000-02 4.00000-04          0          0          6          0 151 8457    2
 4.54609+06 0.00000+00 4.54609+06 0.00000+00 1.26426+06 0.00000+00 151 8457    3
 1.50000+00 1.00000+00          0          0         24          4 151 8457    4
 1.00000+00 0.00000+00 1.58670+07 0.00000+00 6.20500-01 0.00000+00 151 8457    5
 1.50000+00 0.00000+00 1.34897+07 0.00000+00 3.70000-01 0.00000+00 151 8457    6
 1.55000+00 0.00000+00 7.12640+06 0.00000+00 9.00000-03 0.00000+00 151 8457    7
 1.55500+00 0.00000+00 3.45470+06 0.00000+00 5.00000-04 0.00000+00 151 8457    8
                                                                   151 8  099999
                                                                   151 0  0    0
                                                                     0 0  0    0
 1.103200+4 3.174540+1         -1          0          2          1 152 1451    1
 0.000000+0 1.000000+0          0          0          0          6 152 1451    2
 0.000000+0 0.000000+0          0          0          4        311 152 1451    3
 0.000000+0 0.000000+0          0          0         18          2 152 1451    4
 11-Na- 32 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  152 1451    5
                      DIST-NOV07                       261107      152 1451    6
----JEFF-311          MATERIAL  152                                152 1451    7
-----RADIOACTIVE DECAY DATA                                        152 1451    8
------ENDF-6 FORMAT                                                152 1451    9
****************************************************************** 152 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 152 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 152 1451   12
**             Original data taken from:  NUBASE                ** 152 1451   13
****************************************************************** 152 1451   14
****************************************************************** 152 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 152 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      152 1451   17
                                                                   152 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           152 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        152 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               152 1451   21
****************************************************************** 152 1451   22
                                1        451         24          0 152 1451   23
                                8        457          7          0 152 1451   24
 0.000000+0 0.000000+0          0          0          0          0 152 1  099999
                                                                   152 0  0    0
 1.10320+04 3.17454+01          0          0          0          0 152 8457    1
 1.29000-02 7.00000-04          0          0          6          0 152 8457    2
 5.62564+06 0.00000+00 5.62564+06 0.00000+00 1.08891+06 0.00000+00 152 8457    3
-7.77770+01 0.00000+00          0          0         18          3 152 8457    4
 1.00000+00 0.00000+00 2.00150+07 0.00000+00 6.80000-01 0.00000+00 152 8457    5
 1.50000+00 0.00000+00 1.42057+07 0.00000+00 2.40000-01 0.00000+00 152 8457    6
 1.55000+00 0.00000+00 1.18284+07 0.00000+00 8.00000-02 0.00000+00 152 8457    7
                                                                   152 8  099999
                                                                   152 0  0    0
                                                                     0 0  0    0
 1.103300+4 3.274300+1         -1          0          2          1 153 1451    1
 0.000000+0 1.000000+0          0          0          0          6 153 1451    2
 0.000000+0 0.000000+0          0          0          4        311 153 1451    3
 0.000000+0 0.000000+0          0          0         18          2 153 1451    4
 11-Na- 33 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  153 1451    5
                      DIST-NOV07                       261107      153 1451    6
----JEFF-311          MATERIAL  153                                153 1451    7
-----RADIOACTIVE DECAY DATA                                        153 1451    8
------ENDF-6 FORMAT                                                153 1451    9
****************************************************************** 153 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 153 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 153 1451   12
**             Original data taken from:  NUBASE                ** 153 1451   13
****************************************************************** 153 1451   14
****************************************************************** 153 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 153 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      153 1451   17
                                                                   153 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           153 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        153 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               153 1451   21
****************************************************************** 153 1451   22
                                1        451         24          0 153 1451   23
                                8        457          7          0 153 1451   24
 0.000000+0 0.000000+0          0          0          0          0 153 1  099999
                                                                   153 0  0    0
 1.10330+04 3.27430+01          0          0          0          0 153 8457    1
 8.20000-03 2.00000-04          0          0          6          0 153 8457    2
 5.14339+06 0.00000+00 5.14339+06 0.00000+00 2.47725+06 0.00000+00 153 8457    3
 1.50000+00 1.00000+00          0          0         18          3 153 8457    4
 1.00000+00 0.00000+00 1.99960+07 0.00000+00 4.00000-01 0.00000+00 153 8457    5
 1.50000+00 0.00000+00 1.77737+07 0.00000+00 4.70000-01 0.00000+00 153 8457    6
 1.55000+00 0.00000+00 1.19644+07 0.00000+00 1.30000-01 0.00000+00 153 8457    7
                                                                   153 8  099999
                                                                   153 0  0    0
                                                                     0 0  0    0
 1.103400+4 3.374280+1         -1          0          2          1 154 1451    1
 0.000000+0 1.000000+0          0          0          0          6 154 1451    2
 0.000000+0 0.000000+0          0          0          4        311 154 1451    3
 0.000000+0 0.000000+0          0          0         18          2 154 1451    4
 11-Na- 34 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  154 1451    5
                      DIST-NOV07                       261107      154 1451    6
----JEFF-311          MATERIAL  154                                154 1451    7
-----RADIOACTIVE DECAY DATA                                        154 1451    8
------ENDF-6 FORMAT                                                154 1451    9
****************************************************************** 154 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 154 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 154 1451   12
**             Original data taken from:  NUBASE                ** 154 1451   13
****************************************************************** 154 1451   14
****************************************************************** 154 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 154 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      154 1451   17
                                                                   154 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           154 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        154 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               154 1451   21
****************************************************************** 154 1451   22
                                1        451         24          0 154 1451   23
                                8        457          7          0 154 1451   24
 0.000000+0 0.000000+0          0          0          0          0 154 1  099999
                                                                   154 0  0    0
 1.10340+04 3.37428+01          0          0          0          0 154 8457    1
 5.50000-03 1.00000-03          0          0          6          0 154 8457    2
 5.73302+06 0.00000+00 5.73302+06 0.00000+00 2.93885+06 0.00000+00 154 8457    3
 1.00000+00 1.00000+00          0          0         18          3 154 8457    4
 1.00000+00 0.00000+00 2.39500+07 0.00000+00 3.50000-01 0.00000+00 154 8457    5
 1.55000+00 0.00000+00 1.75724+07 0.00000+00 5.00000-01 0.00000+00 154 8457    6
 1.50000+00 0.00000+00 1.97947+07 0.00000+00 1.50000-01 0.00000+00 154 8457    7
                                                                   154 8  099999
                                                                   154 0  0    0
                                                                     0 0  0    0
 1.103500+4 3.474150+1         -1          0          2          1 155 1451    1
 0.000000+0 1.000000+0          0          0          0          6 155 1451    2
 0.000000+0 0.000000+0          0          0          4        311 155 1451    3
 0.000000+0 0.000000+0          0          0         18          2 155 1451    4
 11-Na- 35 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  155 1451    5
                      DIST-NOV07                       261107      155 1451    6
----JEFF-311          MATERIAL  155                                155 1451    7
-----RADIOACTIVE DECAY DATA                                        155 1451    8
------ENDF-6 FORMAT                                                155 1451    9
****************************************************************** 155 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 155 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 155 1451   12
**             Original data taken from:  NUBASE                ** 155 1451   13
****************************************************************** 155 1451   14
****************************************************************** 155 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 155 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      155 1451   17
                                                                   155 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           155 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        155 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               155 1451   21
****************************************************************** 155 1451   22
                                1        451         24          0 155 1451   23
                                8        457          5          0 155 1451   24
 0.000000+0 0.000000+0          0          0          0          0 155 1  099999
                                                                   155 0  0    0
 1.10350+04 3.47415+01          0          0          0          0 155 8457    1
 1.50000-03 5.00000-04          0          0          6          0 155 8457    2
 7.81000+06 0.00000+00 7.81000+06 0.00000+00 0.00000+00 0.00000+00 155 8457    3
 1.50000+00 1.00000+00          0          0          6          1 155 8457    4
 1.00000+00 0.00000+00 2.34300+07 0.00000+00 1.00000+00 0.00000+00 155 8457    5
                                                                   155 8  099999
                                                                   155 0  0    0
                                                                     0 0  0    0
 1.103600+4 3.574180+1         -1          0          2          1 156 1451    1
 0.000000+0 1.000000+0          0          0          0          6 156 1451    2
 0.000000+0 0.000000+0          0          0          4        311 156 1451    3
 0.000000+0 0.000000+0          0          0         18          2 156 1451    4
 11-Na- 36 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  156 1451    5
                      DIST-NOV07                       261107      156 1451    6
----JEFF-311          MATERIAL  156                                156 1451    7
-----RADIOACTIVE DECAY DATA                                        156 1451    8
------ENDF-6 FORMAT                                                156 1451    9
****************************************************************** 156 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 156 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 156 1451   12
**             Original data taken from:  NUBASE                ** 156 1451   13
****************************************************************** 156 1451   14
****************************************************************** 156 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 156 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      156 1451   17
                                                                   156 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           156 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        156 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               156 1451   21
****************************************************************** 156 1451   22
                                1        451         24          0 156 1451   23
                                8        457          5          0 156 1451   24
 0.000000+0 0.000000+0          0          0          0          0 156 1  099999
                                                                   156 0  0    0
 1.10360+04 3.57418+01          0          0          0          0 156 8457    1
 2.60000-07 0.00000+00          0          0          6          0 156 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 2.98699+05 0.00000+00 156 8457    3
-7.77770+01 0.00000+00          0          0          6          1 156 8457    4
 5.00000+00 0.00000+00 2.98699+05 0.00000+00 1.00000+00 0.00000+00 156 8457    5
                                                                   156 8  099999
                                                                   156 0  0    0
                                                                     0 0  0    0
 1.103700+4 3.674100+1         -1          0          2          1 157 1451    1
 0.000000+0 1.000000+0          0          0          0          6 157 1451    2
 0.000000+0 0.000000+0          0          0          4        311 157 1451    3
 0.000000+0 0.000000+0          0          0         18          2 157 1451    4
 11-Na- 37 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT +  157 1451    5
                      DIST-NOV07                       261107      157 1451    6
----JEFF-311          MATERIAL  157                                157 1451    7
-----RADIOACTIVE DECAY DATA                                        157 1451    8
------ENDF-6 FORMAT                                                157 1451    9
****************************************************************** 157 1451   10
**             JEFF-3.11 Radioactive Decay Data File            ** 157 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           ** 157 1451   12
**             Original data taken from:  NUBASE                ** 157 1451   13
****************************************************************** 157 1451   14
****************************************************************** 157 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel) 157 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).      157 1451   17
                                                                   157 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra           157 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties        157 1451   20
      Nucl. Phys. A729 (2003) 3-128.                               157 1451   21
****************************************************************** 157 1451   22
                                1        451         24          0 157 1451   23
                                8        457          5          0 157 1451   24
 0.000000+0 0.000000+0          0          0          0          0 157 1  099999
                                                                   157 0  0    0
 1.10370+04 3.67410+01          0          0          0          0 157 8457    1
 1.00000-03 0.00000+00          0          0          6          0 157 8457    2
 8.67667+06 0.00000+00 8.67667+06 0.00000+00 0.00000+00 0.00000+00 157 8457    3
 1.50000+00 1.00000+00          0          0          6          1 157 8457    4
 1.00000+00 0.00000+00 2.60300+07 0.00000+00 1.00000+00 0.00000+00 157 8457    5
                                                                   157 8  099999
                                                                   157 0  0    0
                                                                     0 0  0    0
