 7.415800+4 1.566170+2         -1          0          2          12691 1451    1
 0.000000+0 1.000000+0          0          0          0          62691 1451    2
 0.000000+0 0.000000+0          0          0          4        3112691 1451    3
 0.000000+0 0.000000+0          0          0         18          22691 1451    4
 74-W -158 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2691 1451    5
                      DIST-NOV07                       261107     2691 1451    6
----JEFF-311          MATERIAL 2691                               2691 1451    7
-----RADIOACTIVE DECAY DATA                                       2691 1451    8
------ENDF-6 FORMAT                                               2691 1451    9
******************************************************************2691 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2691 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2691 1451   12
**             Original data taken from:  NUBASE                **2691 1451   13
******************************************************************2691 1451   14
******************************************************************2691 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2691 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2691 1451   17
                                                                  2691 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2691 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2691 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2691 1451   21
******************************************************************2691 1451   22
                                1        451         24          02691 1451   23
                                8        457          5          02691 1451   24
 0.000000+0 0.000000+0          0          0          0          02691 1  099999
                                                                  2691 0  0    0
 7.41580+04 1.56617+02          0          0          0          02691 8457    1
 1.37000-03 1.70000-04          0          0          6          02691 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 6.60510+06 0.00000+002691 8457    3
 0.00000+00 1.00000+00          0          0          6          12691 8457    4
 4.00000+00 0.00000+00 6.60510+06 0.00000+00 1.00000+00 0.00000+002691 8457    5
                                                                  2691 8  099999
                                                                  2691 0  0    0
                                                                     0 0  0    0
 7.415900+4 1.576070+2         -1          0          2          12692 1451    1
 0.000000+0 1.000000+0          0          0          0          62692 1451    2
 0.000000+0 0.000000+0          0          0          4        3112692 1451    3
 0.000000+0 0.000000+0          0          0         18          22692 1451    4
 74-W -159 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2692 1451    5
                      DIST-NOV07                       261107     2692 1451    6
----JEFF-311          MATERIAL 2692                               2692 1451    7
-----RADIOACTIVE DECAY DATA                                       2692 1451    8
------ENDF-6 FORMAT                                               2692 1451    9
******************************************************************2692 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2692 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2692 1451   12
**             Original data taken from:  NUBASE                **2692 1451   13
******************************************************************2692 1451   14
******************************************************************2692 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2692 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2692 1451   17
                                                                  2692 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2692 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2692 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2692 1451   21
******************************************************************2692 1451   22
                                1        451         24          02692 1451   23
                                8        457          7          02692 1451   24
 0.000000+0 0.000000+0          0          0          0          02692 1  099999
                                                                  2692 0  0    0
 7.41590+04 1.57607+02          0          0          0          02692 8457    1
 8.20000-03 7.00000-04          0          0          6          02692 8457    2
 5.51160+05 0.00000+00 5.51160+05 0.00000+00 5.28498+06 0.00000+002692 8457    3
 3.50000+00-1.00000+00          0          0         18          32692 8457    4
 4.00000+00 0.00000+00 6.44510+06 0.00000+00 8.20000-01 0.00000+002692 8457    5
 2.00000+00 0.00000+00 9.21800+06 0.00000+00 9.00000-02 0.00000+002692 8457    6
 2.00000+00 1.00000+00 9.15400+06 0.00000+00 9.00000-02 0.00000+002692 8457    7
                                                                  2692 8  099999
                                                                  2692 0  0    0
                                                                     0 0  0    0
 7.416000+4 1.585940+2         -1          0          2          12693 1451    1
 0.000000+0 1.000000+0          0          0          0          62693 1451    2
 0.000000+0 0.000000+0          0          0          4        3112693 1451    3
 0.000000+0 0.000000+0          0          0         18          22693 1451    4
 74-W -160 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2693 1451    5
                      DIST-NOV07                       261107     2693 1451    6
----JEFF-311          MATERIAL 2693                               2693 1451    7
-----RADIOACTIVE DECAY DATA                                       2693 1451    8
------ENDF-6 FORMAT                                               2693 1451    9
******************************************************************2693 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2693 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2693 1451   12
**             Original data taken from:  NUBASE                **2693 1451   13
******************************************************************2693 1451   14
******************************************************************2693 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2693 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2693 1451   17
                                                                  2693 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2693 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2693 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2693 1451   21
******************************************************************2693 1451   22
                                1        451         24          02693 1451   23
                                8        457          6          02693 1451   24
 0.000000+0 0.000000+0          0          0          0          02693 1  099999
                                                                  2693 0  0    0
 7.41600+04 1.58594+02          0          0          0          02693 8457    1
 9.00000-02 5.00000-03          0          0          6          02693 8457    2
 2.82533+05 0.00000+00 2.82533+05 0.00000+00 5.27664+06 0.00000+002693 8457    3
 0.00000+00 1.00000+00          0          0         12          22693 8457    4
 4.00000+00 0.00000+00 6.06510+06 0.00000+00 8.70000-01 0.00000+002693 8457    5
 2.00000+00 0.00000+00 6.52000+06 0.00000+00 1.30000-01 0.00000+002693 8457    6
                                                                  2693 8  099999
                                                                  2693 0  0    0
                                                                     0 0  0    0
 7.416100+4 1.595850+2         -1          0          2          12694 1451    1
 0.000000+0 1.000000+0          0          0          0          62694 1451    2
 0.000000+0 0.000000+0          0          0          4        3112694 1451    3
 0.000000+0 0.000000+0          0          0         18          22694 1451    4
 74-W -161 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2694 1451    5
                      DIST-NOV07                       261107     2694 1451    6
----JEFF-311          MATERIAL 2694                               2694 1451    7
-----RADIOACTIVE DECAY DATA                                       2694 1451    8
------ENDF-6 FORMAT                                               2694 1451    9
******************************************************************2694 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2694 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2694 1451   12
**             Original data taken from:  NUBASE                **2694 1451   13
******************************************************************2694 1451   14
******************************************************************2694 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2694 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2694 1451   17
                                                                  2694 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2694 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2694 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2694 1451   21
******************************************************************2694 1451   22
                                1        451         24          02694 1451   23
                                8        457          7          02694 1451   24
 0.000000+0 0.000000+0          0          0          0          02694 1  099999
                                                                  2694 0  0    0
 7.41610+04 1.59585+02          0          0          0          02694 8457    1
 4.09000-01 1.60000-02          0          0          6          02694 8457    2
 7.46550+05 0.00000+00 7.46550+05 0.00000+00 4.31802+06 0.00000+002694 8457    3
 3.50000+00-1.00000+00          0          0         18          32694 8457    4
 4.00000+00 0.00000+00 5.91510+06 0.00000+00 7.30000-01 0.00000+002694 8457    5
 2.00000+00 0.00000+00 8.32000+06 0.00000+00 1.35000-01 0.00000+002694 8457    6
 2.00000+00 1.00000+00 8.27000+06 0.00000+00 1.35000-01 0.00000+002694 8457    7
                                                                  2694 8  099999
                                                                  2694 0  0    0
                                                                     0 0  0    0
 7.416200+4 1.605720+2         -1          0          2          12695 1451    1
 0.000000+0 1.000000+0          0          0          0          62695 1451    2
 0.000000+0 0.000000+0          0          0          4        3112695 1451    3
 0.000000+0 0.000000+0          0          0         18          22695 1451    4
 74-W -162 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2695 1451    5
                      DIST-NOV07                       261107     2695 1451    6
----JEFF-311          MATERIAL 2695                               2695 1451    7
-----RADIOACTIVE DECAY DATA                                       2695 1451    8
------ENDF-6 FORMAT                                               2695 1451    9
******************************************************************2695 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2695 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2695 1451   12
**             Original data taken from:  NUBASE                **2695 1451   13
******************************************************************2695 1451   14
******************************************************************2695 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2695 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2695 1451   17
                                                                  2695 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2695 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2695 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2695 1451   21
******************************************************************2695 1451   22
                                1        451         24          02695 1451   23
                                8        457          6          02695 1451   24
 0.000000+0 0.000000+0          0          0          0          02695 1  099999
                                                                  2695 0  0    0
 7.41620+04 1.60572+02          0          0          0          02695 8457    1
 1.36000+00 7.00000-02          0          0          6          02695 8457    2
 1.05545+06 0.00000+00 1.05545+06 0.00000+00 2.56605+06 0.00000+002695 8457    3
 0.00000+00 1.00000+00          0          0         12          22695 8457    4
 2.00000+00 0.00000+00 5.77800+06 0.00000+00 5.48000-01 0.00000+002695 8457    5
 4.00000+00 0.00000+00 5.67710+06 0.00000+00 4.52000-01 0.00000+002695 8457    6
                                                                  2695 8  099999
                                                                  2695 0  0    0
                                                                     0 0  0    0
 7.416300+4 1.615630+2         -1          0          2          12696 1451    1
 0.000000+0 1.000000+0          0          0          0          62696 1451    2
 0.000000+0 0.000000+0          0          0          4        3112696 1451    3
 0.000000+0 0.000000+0          0          0         18          22696 1451    4
 74-W -163 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2696 1451    5
                      DIST-NOV07                       261107     2696 1451    6
----JEFF-311          MATERIAL 2696                               2696 1451    7
-----RADIOACTIVE DECAY DATA                                       2696 1451    8
------ENDF-6 FORMAT                                               2696 1451    9
******************************************************************2696 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2696 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2696 1451   12
**             Original data taken from:  NUBASE                **2696 1451   13
******************************************************************2696 1451   14
******************************************************************2696 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2696 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2696 1451   17
                                                                  2696 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2696 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2696 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2696 1451   21
******************************************************************2696 1451   22
                                1        451         24          02696 1451   23
                                8        457          6          02696 1451   24
 0.000000+0 0.000000+0          0          0          0          02696 1  099999
                                                                  2696 0  0    0
 7.41630+04 1.61563+02          0          0          0          02696 8457    1
 2.80000+00 2.00000-01          0          0          6          02696 8457    2
 2.21270+06 0.00000+00 2.21270+06 0.00000+00 7.17484+05 0.00000+002696 8457    3
 1.50000+00-1.00000+00          0          0         12          22696 8457    4
 2.00000+00 0.00000+00 7.63000+06 0.00000+00 8.70000-01 0.00000+002696 8457    5
 4.00000+00 0.00000+00 5.51910+06 0.00000+00 1.30000-01 0.00000+002696 8457    6
                                                                  2696 8  099999
                                                                  2696 0  0    0
                                                                     0 0  0    0
 7.416400+4 1.625500+2         -1          0          2          12697 1451    1
 0.000000+0 1.000000+0          0          0          0          62697 1451    2
 0.000000+0 0.000000+0          0          0          4        3112697 1451    3
 0.000000+0 0.000000+0          0          0         18          22697 1451    4
 74-W -164 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2697 1451    5
                      DIST-NOV07                       261107     2697 1451    6
----JEFF-311          MATERIAL 2697                               2697 1451    7
-----RADIOACTIVE DECAY DATA                                       2697 1451    8
------ENDF-6 FORMAT                                               2697 1451    9
******************************************************************2697 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2697 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2697 1451   12
**             Original data taken from:  NUBASE                **2697 1451   13
******************************************************************2697 1451   14
******************************************************************2697 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2697 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2697 1451   17
                                                                  2697 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2697 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2697 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2697 1451   21
******************************************************************2697 1451   22
                                1        451         24          02697 1451   23
                                8        457          6          02697 1451   24
 0.000000+0 0.000000+0          0          0          0          02697 1  099999
                                                                  2697 0  0    0
 7.41640+04 1.62550+02          0          0          0          02697 8457    1
 6.30000+00 2.00000-01          0          0          6          02697 8457    2
 1.61905+06 0.00000+00 1.61905+06 0.00000+00 2.00568+05 0.00000+002697 8457    3
 0.00000+00 1.00000+00          0          0         12          22697 8457    4
 2.00000+00 0.00000+00 5.04900+06 0.00000+00 9.62000-01 0.00000+002697 8457    5
 4.00000+00 0.00000+00 5.27810+06 0.00000+00 3.80000-02 0.00000+002697 8457    6
                                                                  2697 8  099999
                                                                  2697 0  0    0
                                                                     0 0  0    0
 7.416500+4 1.635410+2         -1          0          2          12698 1451    1
 0.000000+0 1.000000+0          0          0          0          62698 1451    2
 0.000000+0 0.000000+0          0          0          4        3112698 1451    3
 0.000000+0 0.000000+0          0          0         18          22698 1451    4
 74-W -165 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2698 1451    5
                      DIST-NOV07                       261107     2698 1451    6
----JEFF-311          MATERIAL 2698                               2698 1451    7
-----RADIOACTIVE DECAY DATA                                       2698 1451    8
------ENDF-6 FORMAT                                               2698 1451    9
******************************************************************2698 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2698 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2698 1451   12
**             Original data taken from:  NUBASE                **2698 1451   13
******************************************************************2698 1451   14
******************************************************************2698 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2698 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2698 1451   17
                                                                  2698 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2698 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2698 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2698 1451   21
******************************************************************2698 1451   22
                                1        451         24          02698 1451   23
                                8        457          6          02698 1451   24
 0.000000+0 0.000000+0          0          0          0          02698 1  099999
                                                                  2698 0  0    0
 7.41650+04 1.63541+02          0          0          0          02698 8457    1
 5.10000+00 5.00000-01          0          0          6          02698 8457    2
 2.32634+06 0.00000+00 2.32634+06 0.00000+00 1.00642+04 0.00000+002698 8457    3
 1.50000+00-1.00000+00          0          0         12          22698 8457    4
 2.00000+00 0.00000+00 6.99300+06 0.00000+00 9.98000-01 0.00000+002698 8457    5
 4.00000+00 0.00000+00 5.03210+06 0.00000+00 2.00000-03 0.00000+002698 8457    6
                                                                  2698 8  099999
                                                                  2698 0  0    0
                                                                     0 0  0    0
 7.416600+4 1.645290+2         -1          0          2          12699 1451    1
 0.000000+0 1.000000+0          0          0          0          62699 1451    2
 0.000000+0 0.000000+0          0          0          4        3112699 1451    3
 0.000000+0 0.000000+0          0          0         18          22699 1451    4
 74-W -166 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2699 1451    5
                      DIST-NOV07                       261107     2699 1451    6
----JEFF-311          MATERIAL 2699                               2699 1451    7
-----RADIOACTIVE DECAY DATA                                       2699 1451    8
------ENDF-6 FORMAT                                               2699 1451    9
******************************************************************2699 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2699 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2699 1451   12
**             Original data taken from:  NUBASE                **2699 1451   13
******************************************************************2699 1451   14
******************************************************************2699 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2699 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2699 1451   17
                                                                  2699 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2699 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2699 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2699 1451   21
******************************************************************2699 1451   22
                                1        451         24          02699 1451   23
                                8        457          6          02699 1451   24
 0.000000+0 0.000000+0          0          0          0          02699 1  099999
                                                                  2699 0  0    0
 7.41660+04 1.64529+02          0          0          0          02699 8457    1
 1.92000+01 6.00000-01          0          0          6          02699 8457    2
 1.40151+06 0.00000+00 1.40151+06 0.00000+00 1.69964+03 0.00000+002699 8457    3
 0.00000+00 1.00000+00          0          0         12          22699 8457    4
 2.00000+00 0.00000+00 4.20600+06 0.00000+00 9.99650-01 0.00000+002699 8457    5
 4.00000+00 0.00000+00 4.85610+06 0.00000+00 3.50000-04 0.00000+002699 8457    6
                                                                  2699 8  099999
                                                                  2699 0  0    0
                                                                     0 0  0    0
 7.416700+4 1.655210+2         -1          0          2          12700 1451    1
 0.000000+0 1.000000+0          0          0          0          62700 1451    2
 0.000000+0 0.000000+0          0          0          4        3112700 1451    3
 0.000000+0 0.000000+0          0          0         18          22700 1451    4
 74-W -167 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2700 1451    5
                      DIST-NOV07                       261107     2700 1451    6
----JEFF-311          MATERIAL 2700                               2700 1451    7
-----RADIOACTIVE DECAY DATA                                       2700 1451    8
------ENDF-6 FORMAT                                               2700 1451    9
******************************************************************2700 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2700 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2700 1451   12
**             Original data taken from:  NUBASE                **2700 1451   13
******************************************************************2700 1451   14
******************************************************************2700 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2700 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2700 1451   17
                                                                  2700 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2700 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2700 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2700 1451   21
******************************************************************2700 1451   22
                                1        451         24          02700 1451   23
                                8        457          6          02700 1451   24
 0.000000+0 0.000000+0          0          0          0          02700 1  099999
                                                                  2700 0  0    0
 7.41670+04 1.65521+02          0          0          0          02700 8457    1
 1.99000+01 5.00000-01          0          0          6          02700 8457    2
 2.08650+06 0.00000+00 2.08650+06 0.00000+00 1.90884+03 0.00000+002700 8457    3
 1.50000+00-1.00000+00          0          0         12          22700 8457    4
 2.00000+00 0.00000+00 6.26200+06 0.00000+00 9.99600-01 0.00000+002700 8457    5
 4.00000+00 0.00000+00 4.77210+06 0.00000+00 4.00000-04 0.00000+002700 8457    6
                                                                  2700 8  099999
                                                                  2700 0  0    0
                                                                     0 0  0    0
 7.416800+4 1.665090+2         -1          0          2          12701 1451    1
 0.000000+0 1.000000+0          0          0          0          62701 1451    2
 0.000000+0 0.000000+0          0          0          4        3112701 1451    3
 0.000000+0 0.000000+0          0          0         18          22701 1451    4
 74-W -168 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2701 1451    5
                      DIST-NOV07                       261107     2701 1451    6
----JEFF-311          MATERIAL 2701                               2701 1451    7
-----RADIOACTIVE DECAY DATA                                       2701 1451    8
------ENDF-6 FORMAT                                               2701 1451    9
******************************************************************2701 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2701 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2701 1451   12
**             Original data taken from:  NUBASE                **2701 1451   13
******************************************************************2701 1451   14
******************************************************************2701 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2701 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2701 1451   17
                                                                  2701 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2701 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2701 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2701 1451   21
******************************************************************2701 1451   22
                                1        451         24          02701 1451   23
                                8        457          6          02701 1451   24
 0.000000+0 0.000000+0          0          0          0          02701 1  099999
                                                                  2701 0  0    0
 7.41680+04 1.66509+02          0          0          0          02701 8457    1
 5.10000+01 2.00000+00          0          0          6          02701 8457    2
 1.16796+06 0.00000+00 1.16796+06 0.00000+00 1.44227+02 0.00000+002701 8457    3
 0.00000+00 1.00000+00          0          0         12          22701 8457    4
 2.00000+00 0.00000+00 3.50400+06 0.00000+00 9.99968-01 0.00000+002701 8457    5
 4.00000+00 0.00000+00 4.50710+06 0.00000+00 3.20000-05 0.00000+002701 8457    6
                                                                  2701 8  099999
                                                                  2701 0  0    0
                                                                     0 0  0    0
 7.416900+4 1.675000+2         -1          0          2          12702 1451    1
 0.000000+0 1.000000+0          0          0          0          62702 1451    2
 0.000000+0 0.000000+0          0          0          4        3112702 1451    3
 0.000000+0 0.000000+0          0          0         18          22702 1451    4
 74-W -169 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2702 1451    5
                      DIST-NOV07                       261107     2702 1451    6
----JEFF-311          MATERIAL 2702                               2702 1451    7
-----RADIOACTIVE DECAY DATA                                       2702 1451    8
------ENDF-6 FORMAT                                               2702 1451    9
******************************************************************2702 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2702 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2702 1451   12
**             Original data taken from:  NUBASE                **2702 1451   13
******************************************************************2702 1451   14
******************************************************************2702 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2702 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2702 1451   17
                                                                  2702 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2702 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2702 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2702 1451   21
******************************************************************2702 1451   22
                                1        451         24          02702 1451   23
                                8        457          5          02702 1451   24
 0.000000+0 0.000000+0          0          0          0          02702 1  099999
                                                                  2702 0  0    0
 7.41690+04 1.67500+02          0          0          0          02702 8457    1
 7.60000+01 6.00000+00          0          0          6          02702 8457    2
 1.79067+06 0.00000+00 1.79067+06 0.00000+00 0.00000+00 0.00000+002702 8457    3
 2.50000+00-1.00000+00          0          0          6          12702 8457    4
 2.00000+00 0.00000+00 5.37200+06 0.00000+00 1.00000+00 0.00000+002702 8457    5
                                                                  2702 8  099999
                                                                  2702 0  0    0
                                                                     0 0  0    0
 7.417000+4 1.684890+2         -1          0          2          12703 1451    1
 0.000000+0 1.000000+0          0          0          0          62703 1451    2
 0.000000+0 0.000000+0          0          0          4        3112703 1451    3
 0.000000+0 0.000000+0          0          0         18          22703 1451    4
 74-W -170 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2703 1451    5
                      DIST-NOV07                       261107     2703 1451    6
----JEFF-311          MATERIAL 2703                               2703 1451    7
-----RADIOACTIVE DECAY DATA                                       2703 1451    8
------ENDF-6 FORMAT                                               2703 1451    9
******************************************************************2703 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2703 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2703 1451   12
**             Original data taken from:  NUBASE                **2703 1451   13
******************************************************************2703 1451   14
******************************************************************2703 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2703 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2703 1451   17
                                                                  2703 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2703 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2703 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2703 1451   21
******************************************************************2703 1451   22
                                1        451         24          02703 1451   23
                                8        457          6          02703 1451   24
 0.000000+0 0.000000+0          0          0          0          02703 1  099999
                                                                  2703 0  0    0
 7.41700+04 1.68489+02          0          0          0          02703 8457    1
 1.45200+02 2.40000+00          0          0          6          02703 8457    2
 9.38849+05 0.00000+00 9.38849+05 0.00000+00 4.14110+04 0.00000+002703 8457    3
 0.00000+00 1.00000+00          0          0         12          22703 8457    4
 2.00000+00 0.00000+00 2.84500+06 0.00000+00 9.90000-01 0.00000+002703 8457    5
 4.00000+00 0.00000+00 4.14110+06 0.00000+00 1.00000-02 0.00000+002703 8457    6
                                                                  2703 8  099999
                                                                  2703 0  0    0
                                                                     0 0  0    0
 7.417100+4 1.694810+2         -1          0          2          12704 1451    1
 0.000000+0 1.000000+0          0          0          0          62704 1451    2
 0.000000+0 0.000000+0          0          0          4        3112704 1451    3
 0.000000+0 0.000000+0          0          0         18          22704 1451    4
 74-W -171 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2704 1451    5
                      DIST-NOV07                       261107     2704 1451    6
----JEFF-311          MATERIAL 2704                               2704 1451    7
-----RADIOACTIVE DECAY DATA                                       2704 1451    8
------ENDF-6 FORMAT                                               2704 1451    9
******************************************************************2704 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2704 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2704 1451   12
**             Original data taken from:  NUBASE                **2704 1451   13
******************************************************************2704 1451   14
******************************************************************2704 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2704 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2704 1451   17
                                                                  2704 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2704 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2704 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2704 1451   21
******************************************************************2704 1451   22
                                1        451         24          02704 1451   23
                                8        457          5          02704 1451   24
 0.000000+0 0.000000+0          0          0          0          02704 1  099999
                                                                  2704 0  0    0
 7.41710+04 1.69481+02          0          0          0          02704 8457    1
 1.42800+02 2.40000+00          0          0          6          02704 8457    2
 1.54467+06 0.00000+00 1.54467+06 0.00000+00 0.00000+00 0.00000+002704 8457    3
 2.50000+00-1.00000+00          0          0          6          12704 8457    4
 2.00000+00 0.00000+00 4.63400+06 0.00000+00 1.00000+00 0.00000+002704 8457    5
                                                                  2704 8  099999
                                                                  2704 0  0    0
                                                                     0 0  0    0
 7.417200+4 1.704700+2         -1          0          2          12705 1451    1
 0.000000+0 1.000000+0          0          0          0          62705 1451    2
 0.000000+0 0.000000+0          0          0          4        3112705 1451    3
 0.000000+0 0.000000+0          0          0         18          22705 1451    4
 74-W -172 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2705 1451    5
                      DIST-NOV07                       261107     2705 1451    6
----JEFF-311          MATERIAL 2705                               2705 1451    7
-----RADIOACTIVE DECAY DATA                                       2705 1451    8
------ENDF-6 FORMAT                                               2705 1451    9
******************************************************************2705 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2705 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2705 1451   12
**             Original data taken from:  NUBASE                **2705 1451   13
******************************************************************2705 1451   14
******************************************************************2705 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2705 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2705 1451   17
                                                                  2705 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2705 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2705 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2705 1451   21
******************************************************************2705 1451   22
                                1        451         24          02705 1451   23
                                8        457          5          02705 1451   24
 0.000000+0 0.000000+0          0          0          0          02705 1  099999
                                                                  2705 0  0    0
 7.41720+04 1.70470+02          0          0          0          02705 8457    1
 3.96000+02 5.40000+01          0          0          6          02705 8457    2
 7.44333+05 0.00000+00 7.44333+05 0.00000+00 0.00000+00 0.00000+002705 8457    3
 0.00000+00 1.00000+00          0          0          6          12705 8457    4
 2.00000+00 0.00000+00 2.23300+06 0.00000+00 1.00000+00 0.00000+002705 8457    5
                                                                  2705 8  099999
                                                                  2705 0  0    0
                                                                     0 0  0    0
 7.417300+4 1.714620+2         -1          0          2          12706 1451    1
 0.000000+0 1.000000+0          0          0          0          62706 1451    2
 0.000000+0 0.000000+0          0          0          4        3112706 1451    3
 0.000000+0 0.000000+0          0          0         18          22706 1451    4
 74-W -173 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2706 1451    5
                      DIST-NOV07                       261107     2706 1451    6
----JEFF-311          MATERIAL 2706                               2706 1451    7
-----RADIOACTIVE DECAY DATA                                       2706 1451    8
------ENDF-6 FORMAT                                               2706 1451    9
******************************************************************2706 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2706 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2706 1451   12
**             Original data taken from:  NUBASE                **2706 1451   13
******************************************************************2706 1451   14
******************************************************************2706 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2706 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2706 1451   17
                                                                  2706 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2706 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2706 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2706 1451   21
******************************************************************2706 1451   22
                                1        451         24          02706 1451   23
                                8        457          5          02706 1451   24
 0.000000+0 0.000000+0          0          0          0          02706 1  099999
                                                                  2706 0  0    0
 7.41730+04 1.71462+02          0          0          0          02706 8457    1
 4.56000+02 1.20000+01          0          0          6          02706 8457    2
 1.22333+06 0.00000+00 1.22333+06 0.00000+00 0.00000+00 0.00000+002706 8457    3
 2.50000+00-1.00000+00          0          0          6          12706 8457    4
 2.00000+00 0.00000+00 3.67000+06 0.00000+00 1.00000+00 0.00000+002706 8457    5
                                                                  2706 8  099999
                                                                  2706 0  0    0
                                                                     0 0  0    0
 7.417400+4 1.724520+2         -1          0          2          12707 1451    1
 0.000000+0 1.000000+0          0          0          0          62707 1451    2
 0.000000+0 0.000000+0          0          0          4        3112707 1451    3
 0.000000+0 0.000000+0          0          0         18          22707 1451    4
 74-W -174 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2707 1451    5
                      DIST-NOV07                       261107     2707 1451    6
----JEFF-311          MATERIAL 2707                               2707 1451    7
-----RADIOACTIVE DECAY DATA                                       2707 1451    8
------ENDF-6 FORMAT                                               2707 1451    9
******************************************************************2707 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2707 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2707 1451   12
**             Original data taken from:  NUBASE                **2707 1451   13
******************************************************************2707 1451   14
******************************************************************2707 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2707 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2707 1451   17
                                                                  2707 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2707 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2707 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2707 1451   21
******************************************************************2707 1451   22
                                1        451         24          02707 1451   23
                                8        457          5          02707 1451   24
 0.000000+0 0.000000+0          0          0          0          02707 1  099999
                                                                  2707 0  0    0
 7.41740+04 1.72452+02          0          0          0          02707 8457    1
 1.99200+03 1.26000+02          0          0          6          02707 8457    2
 5.04667+05 0.00000+00 5.04667+05 0.00000+00 0.00000+00 0.00000+002707 8457    3
 0.00000+00 1.00000+00          0          0          6          12707 8457    4
 2.00000+00 0.00000+00 1.51400+06 0.00000+00 1.00000+00 0.00000+002707 8457    5
                                                                  2707 8  099999
                                                                  2707 0  0    0
                                                                     0 0  0    0
 7.417500+4 1.734440+2         -1          0          2          12708 1451    1
 0.000000+0 1.000000+0          0          0          0          62708 1451    2
 0.000000+0 0.000000+0          0          0          4        3112708 1451    3
 0.000000+0 0.000000+0          0          0         18          22708 1451    4
 74-W -175 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2708 1451    5
                      DIST-NOV07                       261107     2708 1451    6
----JEFF-311          MATERIAL 2708                               2708 1451    7
-----RADIOACTIVE DECAY DATA                                       2708 1451    8
------ENDF-6 FORMAT                                               2708 1451    9
******************************************************************2708 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2708 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2708 1451   12
**             Original data taken from:  NUBASE                **2708 1451   13
******************************************************************2708 1451   14
******************************************************************2708 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2708 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2708 1451   17
                                                                  2708 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2708 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2708 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2708 1451   21
******************************************************************2708 1451   22
                                1        451         24          02708 1451   23
                                8        457          5          02708 1451   24
 0.000000+0 0.000000+0          0          0          0          02708 1  099999
                                                                  2708 0  0    0
 7.41750+04 1.73444+02          0          0          0          02708 8457    1
 2.11200+03 3.60000+01          0          0          6          02708 8457    2
 9.25334+05 0.00000+00 9.25334+05 0.00000+00 0.00000+00 0.00000+002708 8457    3
 5.00000-01-1.00000+00          0          0          6          12708 8457    4
 2.00000+00 0.00000+00 2.77600+06 0.00000+00 1.00000+00 0.00000+002708 8457    5
                                                                  2708 8  099999
                                                                  2708 0  0    0
                                                                     0 0  0    0
 7.417600+4 1.744340+2         -1          0          2          12709 1451    1
 0.000000+0 1.000000+0          0          0          0          62709 1451    2
 0.000000+0 0.000000+0          0          0          4        3112709 1451    3
 0.000000+0 0.000000+0          0          0         67          22709 1451    4
 74-W -176 HAR+WIN    EVAL-SEP03 A.L. NICHOLS                     2709 1451    5
                      DIST-NOV07                       261107     2709 1451    6
----JEFF-311          MATERIAL 2709                               2709 1451    7
-----RADIOACTIVE DECAY DATA                                       2709 1451    8
------ENDF-6 FORMAT                                               2709 1451    9
******************************************************************2709 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2709 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2709 1451   12
**             Original data taken from:  UKPADD67              **2709 1451   13
******************************************************************2709 1451   14
                                                                  2709 1451   15
     E Browne, Huo Junde    Nucl Data Sheets 84(1998)337          2709 1451   16
     J Valentin, A Santoni  Nucl Phys 47(1963)303                 2709 1451   17
                            (T1/2, Ece, Pce, Egamma, Pgamma)      2709 1451   18
     E P Grigor'ev et al    Bull Acad Sci USSR                    2709 1451   19
                            Phys Ser 26(1963)118 (T1/2)           2709 1451   20
     C L Rao, L Yaffe       Can J Chem 32(1963)2516 (T1/2)        2709 1451   21
     T V Malysheva et al    Bull Acad Sci USSR                    2709 1451   22
                            Phys Ser 27(1964)1242 (T1/2)          2709 1451   23
     F Rosel et al          At Data Nucl Data Tables 21(1978)92   2709 1451   24
                            (ICC)                                 2709 1451   25
                                                                  2709 1451   26
An extremely uncertain decay scheme has been derived from the     2709 1451   27
decay-data studies of Valentin and Santoni.  Relative K, L and    2709 1451   28
M conversion-electron emission probabilities have been            2709 1451   29
determined by Valentin and Santoni, and these data were summed    2709 1451   30
and used in conjunction with the internal conversion              2709 1451   31
coefficients of Rosel et al to estimate the relative gamma-ray    2709 1451   32
emission probabilities.  EC decay to the 133.8- (2+) and 0.0-keV  2709 1451   33
(1-) nuclear levels of Ta-176 were assumed to be zero on the      2709 1451   34
basis of the observations and suggestions of Valentin and         2709 1451   35
Santoni (and possible spin/parity considerations).  Other         2709 1451   36
significant assumptions included the assigned spins and           2709 1451   37
parities of the various postulated nuclear levels of Ta-176,      2709 1451   38
resulting in the 33.58 and 100.20-keV gamma rays being defined    2709 1451   39
as E2 and E1, respectively; a1l M1 + E2 gamma transitions were    2709 1451   40
specified as 100%M1 (50.55-, 61.29-, 84.14- and 94.86-keV gamma   2709 1451   41
rays); an arbitrary adjustment was also made to the relative      2709 1451   42
emission probability of the 61.29-keV gamma ray to ensure the     2709 1451   43
desired population-depopulation balance for the 133.8-keV         2709 1451   44
nuclear level of Ta-176 (relative gamma-ray emission              2709 1451   45
probability decreased from 124(12) to 74(7) which results in a    2709 1451   46
much reduced relative conversion-electron emission probability    2709 1451   47
than listed by Valentin and Santoni).                             2709 1451   48
                                                                  2709 1451   49
There are significant uncertainties associated with all           2709 1451   50
features of the proposed decay scheme, and a number of            2709 1451   51
questionable assumptions have been made to derive a complete      2709 1451   52
and reasonably consistent data set.  Further gamma-ray            2709 1451   53
measurements are required to confirm, clarify and resolve         2709 1451   54
specific aspects of the decay scheme (i.e., recommended           2709 1451   55
relative gamma-ray emission probabilities and EC transition       2709 1451   56
probabilities).                                                   2709 1451   57
                                                                  2709 1451   58
                                                                  2709 1451   59
      MEAN GAMMA ENERGY              =     83.8302  KEV           2709 1451   60
      BETA+ + NEUTRINO ENERGY        =    617.1300  KEV           2709 1451   61
      MEAN X-RAY ENERGY              =     87.6453  KEV           2709 1451   62
      MEAN AUGER ELECTRON ENERGY     =     16.7494  KEV           2709 1451   63
      MEAN CONVERSION ELECTRON ENERGY=     40.5475  KEV           2709 1451   64
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.0573  KEV           2709 1451   65
      EFFECTIVE Q VALUE              =    791.0000  KEV           2709 1451   66
      UNCERTAINTY IN EFFECTIVE Q (%) =      2.5284                2709 1451   67
      CALCULATED Q VALUE             =    789.9343  KEV           2709 1451   68
      % DEVIATION                    =      0.1347                2709 1451   69
                                                                  2709 1451   70
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2709 1451   71
                                1        451         73          12709 1451   72
                                8        457         90          12709 1451   73
 0.000000+0 0.000000+0          0          0          0          02709 1  099999
 0.000000+0 0.000000+0          0          0          0          02709 0  0    0
 7.417600+4 1.744340+2          0          0          0          42709 8457    1
 9.000000+3 3.600000+2          0          0         34          02709 8457    2
 5.729690+4 4.387080+3 1.715330+5 1.303150+4 0.000000+0 0.000000+02709 8457    3
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 1.674940+4 1.674940+32709 8457    4
 4.054750+4 4.054750+3 8.383020+4 9.643840+3 8.764530+4 8.764530+32709 8457    5
 5.732270+1 5.732270+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02709 8457    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02709 8457    7
 0.000000+0 0.000000+0 6.171300+5 3.964860+4                      2709 8457    8
 0.000000+0 1.000000+0          0          0          6          12709 8457    9
 2.000000+0 0.000000+0 7.910000+5 2.000000+4 1.000000+0 0.000000+02709 8457   10
 0.000000+0 0.000000+0          0          0          6          62709 8457   11
 7.310100-1 5.310000-2 8.383020+4 9.643840+3 0.000000+0 0.000000+02709 8457   12
 3.358000+4 5.000000+1          0          0         12          02709 8457   13
 2.000000+0 0.000000+0 3.841810-4 3.954800-5 0.000000+0 0.000000+02709 8457   14
 5.650000+2 1.130000+1 0.000000+0 0.000000+0 4.230000+2 8.460000+02709 8457   15
 5.055000+4 5.000000+1          0          0         12          02709 8457   16
 2.000000+0 0.000000+0 5.649720-3 5.649720-4 0.000000+0 0.000000+02709 8457   17
 5.650000+0 1.073500-1 0.000000+0 0.000000+0 4.370000+0 8.303000-22709 8457   18
 6.129000+4 5.000000+1          0          0         12          02709 8457   19
 2.000000+0 0.000000+0 4.180790-2 3.954800-3 0.000000+0 0.000000+02709 8457   20
 3.210000+0 6.099000-2 0.000000+0 0.000000+0 2.480000+0 4.712000-22709 8457   21
 8.414000+4 4.000000+1          0          0         12          02709 8457   22
 2.000000+0 0.000000+0 4.124290-2 3.954800-3 0.000000+0 0.000000+02709 8457   23
 7.490000+0 1.498000-1 6.220000+0 1.244000-1 9.800000-1 1.960000-22709 8457   24
 9.486000+4 5.000000+1          0          0         12          02709 8457   25
 2.000000+0 0.000000+0 8.587570-2 8.474580-3 0.000000+0 0.000000+02709 8457   26
 5.300000+0 1.113000-1 4.400000+0 9.240000-2 6.900000-1 1.449000-22709 8457   27
 1.002000+5 5.000000+1          0          0         12          02709 8457   28
 2.000000+0 0.000000+0 1.000000+0 1.016950-1 0.000000+0 0.000000+02709 8457   29
 3.670000-1 6.973000-3 2.990000-1 5.681000-3 5.200000-2 9.880000-42709 8457   30
 0.000000+0 2.000000+0          0          0          6          32709 8457   31
 1.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02709 8457   32
 5.960000+5 2.000000+4          0          0          6          02709 8457   33
 2.000000+0 1.000000+0 5.300000-1 5.000000-2 0.000000+0 0.000000+02709 8457   34
 6.070000+5 2.100000+4          0          0          6          02709 8457   35
 2.000000+0 1.000000+0 2.800000-1 3.000000-2 0.000000+0 0.000000+02709 8457   36
 6.910000+5 2.000000+4          0          0          6          02709 8457   37
 2.000000+0 1.000000+0 1.900000-1 2.000000-2 0.000000+0 0.000000+02709 8457   38
 0.000000+0 8.000000+0          0          0          6         182709 8457   39
 1.000000+0 0.000000+0 5.729690+4 5.729690+3 0.000000+0 0.000000+02709 8457   40
 2.180000+3 1.090000+2          0          0          6          02709 8457   41
 2.000000+0 0.000000+0 2.655940+0 2.655940-1 0.000000+0 0.000000+02709 8457   42
 6.353000+3 3.176500+2          0          0          6          02709 8457   43
 2.000000+0 0.000000+0 1.214660+0 1.214660-1 0.000000+0 0.000000+02709 8457   44
 1.672360+4 8.361800+2          0          0          6          02709 8457   45
 2.000000+0 0.000000+0 1.875270-1 1.875270-2 0.000000+0 0.000000+02709 8457   46
 2.369890+4 1.184950+3          0          0          6          02709 8457   47
 2.000000+0 0.000000+0 1.187950-1 1.187950-2 0.000000+0 0.000000+02709 8457   48
 2.744360+4 1.372180+3          0          0          6          02709 8457   49
 2.000000+0 0.000000+0 2.762140-1 2.762140-2 0.000000+0 0.000000+02709 8457   50
 3.140000+4 1.570000+3          0          0          6          02709 8457   51
 2.000000+0 0.000000+0 3.987930-2 3.987930-3 0.000000+0 0.000000+02709 8457   52
 3.278360+4 1.639180+3          0          0          6          02709 8457   53
 2.000000+0 0.000000+0 2.185720-1 2.185720-2 0.000000+0 0.000000+02709 8457   54
 4.066890+4 2.033440+3          0          0          6          02709 8457   55
 2.000000+0 0.000000+0 1.804810-2 1.804810-3 0.000000+0 0.000000+02709 8457   56
 4.837000+4 2.418500+3          0          0          6          02709 8457   57
 2.000000+0 0.000000+0 5.286400-3 5.286400-4 0.000000+0 0.000000+02709 8457   58
 4.965300+4 2.482650+3          0          0          6          02709 8457   59
 2.000000+0 0.000000+0 6.530770-2 6.530770-3 0.000000+0 0.000000+02709 8457   60
 5.140890+4 2.570450+3          0          0          6          02709 8457   61
 2.000000+0 0.000000+0 7.579380-2 7.579380-3 0.000000+0 0.000000+02709 8457   62
 5.911000+4 2.955500+3          0          0          6          02709 8457   63
 2.000000+0 0.000000+0 2.231030-2 2.231030-3 0.000000+0 0.000000+02709 8457   64
 7.425890+4 3.712950+3          0          0          6          02709 8457   65
 2.000000+0 0.000000+0 2.954600-2 2.954600-3 0.000000+0 0.000000+02709 8457   66
 8.196000+4 4.098000+3          0          0          6          02709 8457   67
 2.000000+0 0.000000+0 8.743210-3 8.743210-4 0.000000+0 0.000000+02709 8457   68
 8.497890+4 4.248940+3          0          0          6          02709 8457   69
 2.000000+0 0.000000+0 4.331540-2 4.331540-3 0.000000+0 0.000000+02709 8457   70
 9.031890+4 4.515940+3          0          0          6          02709 8457   71
 2.000000+0 0.000000+0 3.801250-2 3.801250-3 0.000000+0 0.000000+02709 8457   72
 9.268000+4 4.634000+3          0          0          6          02709 8457   73
 2.000000+0 0.000000+0 1.318300-2 1.318300-3 0.000000+0 0.000000+02709 8457   74
 9.802000+4 4.901000+3          0          0          6          02709 8457   75
 2.000000+0 0.000000+0 1.169620-2 1.169620-3 0.000000+0 0.000000+02709 8457   76
 0.000000+0 9.000000+0          0          0          6          62709 8457   77
 1.000000+0 0.000000+0 8.764530+4 8.764530+3 0.000000+0 0.000000+02709 8457   78
 2.180000+3 4.360000+1          0          0          6          02709 8457   79
 2.000000+0 0.000000+0 4.538220-2 4.538220-3 0.000000+0 0.000000+02709 8457   80
 8.331000+3 1.666200+2          0          0          6          02709 8457   81
 2.000000+0 0.000000+0 4.817930-1 4.817940-2 0.000000+0 0.000000+02709 8457   82
 5.627700+4 1.125540+3          0          0          6          02709 8457   83
 2.000000+0 0.000000+0 4.080570-1 4.080570-2 0.000000+0 0.000000+02709 8457   84
 5.753200+4 1.150640+3          0          0          6          02709 8457   85
 2.000000+0 0.000000+0 7.109010-1 7.109010-2 0.000000+0 0.000000+02709 8457   86
 6.520000+4 1.304000+3          0          0          6          02709 8457   87
 2.000000+0 0.000000+0 2.395740-1 2.395740-2 0.000000+0 0.000000+02709 8457   88
 6.700000+4 1.340000+3          0          0          6          02709 8457   89
 2.000000+0 0.000000+0 6.042660-2 6.042660-3 0.000000+0 0.000000+02709 8457   90
 0.000000+0 0.000000+0          0          0          0          02709 8  099999
 0.000000+0 0.000000+0          0          0          0          02709 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
 7.417700+4 1.754270+2         -1          0          2          12710 1451    1
 0.000000+0 1.000000+0          0          0          0          62710 1451    2
 0.000000+0 0.000000+0          0          0          4        3112710 1451    3
 0.000000+0 0.000000+0          0          0         52          22710 1451    4
 74-W -177 ENSDF      EVAL-MAY03 CONVERSION OF ENSDF              2710 1451    5
 /ENSDF/              DIST-NOV07                       261107     2710 1451    6
----JEFF-311          MATERIAL 2710                               2710 1451    7
-----RADIOACTIVE DECAY DATA                                       2710 1451    8
------ENDF-6 FORMAT                                               2710 1451    9
******************************************************************2710 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2710 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2710 1451   12
**             Original data taken from:  ENSDF                 **2710 1451   13
******************************************************************2710 1451   14
******************************************************************2710 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2710 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2710 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2710 1451   18
******************************************************************2710 1451   19
177W  DECAY 132 M     2                     I(min) = 0.0E+00 %    2710 1451   20
         Ex = 0.0         keV                     1 decay mode(s) 2710 1451   21
                                                                  2710 1451   22
177W EC DECAY               Q =  2001.0000 keV       0.0000       2710 1451   23
         Branching                100.0000 %         0.0000       2710 1451   24
                         Br*Q =  2001.0000 keV       0.0000       2710 1451   25
                                              0 isomeric state(s) 2710 1451   26
                                                                  2710 1451   27
Individual beta+ transitions                                      2710 1451   28
Final level    end point    shape    av.energy        intensity   2710 1451   29
  864.920    114.080   0.070  0     63.000   0.000    0.000 0.000 2710 1451   30
  690.300    288.698   0.100  0    147.000   0.000    0.000 0.000 2710 1451   31
  639.950    339.048   0.070  1    180.000   0.000    0.000 0.000 2710 1451   32
  497.410    481.586   0.060  0    235.000   0.000    0.000 0.000 2710 1451   33
  487.620    491.376   0.060  0    239.000   0.000    0.017 0.001 2710 1451   34
  372.570    606.424   0.070  0    290.000   0.000    0.011 0.002 2710 1451   35
  216.620    762.373   0.070  0    359.000   0.000    0.210 0.010 2710 1451   36
                                                                  2710 1451   37
         Mean alpha    energy       0.0000 keV       0.0000       2710 1451   38
         Mean beta     energy       0.8262 keV       0.0364       2710 1451   39
         Mean conv. e- energy      68.0351 keV       1.7198       2710 1451   40
         Mean Auger e- energy      13.0065 keV       1.4802       2710 1451   41
         Mean gamma    energy     723.0273 keV                    2710 1451   42
         Mean X        energy      92.2756 keV       2.1739       2710 1451   43
         Mean recoil   energy       0.0002 keV       0.0000       2710 1451   44
         Mean neutrino energy    1090.3428 keV      38.2539       2710 1451   45
         Mean neutron  energy       0.0000 keV       0.0000       2710 1451   46
         Total         energy    1987.5153 keV      40.1414       2710 1451   47
         Q effective             2001.0000 keV       0.0000       2710 1451   48
         diff. mode               -13.4847 keV      -0.6739 %     2710 1451   49
                                                                  2710 1451   50
         Mean e- bind. energy     115.6751 keV                    2710 1451   51
         diff. atomic             -10.3929 keV      -8.9846 %     2710 1451   52
         diff. nuclear             -3.0918 keV      -0.1545 %     2710 1451   53
                                                                  2710 1451   54
         B+ fraction                0.2379 %         0.0102       2710 1451   55
                                                                  2710 1451   56
                                1        451         58          02710 1451   57
                                8        457        725          02710 1451   58
 0.000000+0 0.000000+0          0          0          0          02710 1  099999
                                                                  2710 0  0    0
 7.41770+04 1.75427+02          0          0          0          42710 8457    1
 7.92000+03 1.20000+02          0          0          6          02710 8457    2
 8.18678+04 2.26936+03 8.15303+05 1.19508+04 0.00000+00 0.00000+002710 8457    3
 5.00000-01-1.00000+00          0          0          6          12710 8457    4
 2.00000+00 0.00000+00 2.00100+06 0.00000+00 1.00000+00 0.00000+002710 8457    5
 0.00000+00 0.00000+00          0          0          6         742710 8457    6
 1.00000-02 0.00000+00 7.20596+05 1.17509+04 0.00000+00 0.00000+002710 8457    7
 1.39000+04 0.00000+00          0          0         12          02710 8457    8
 2.00000+00 0.00000+00 1.26000-01 8.91964-03 0.00000+00 0.00000+002710 8457    9
 1.43000+01 0.00000+00 0.00000+00 0.00000+00 1.15500+01 3.46500-012710 8457   10
 3.04500+04 5.00000+01          0          0         12          02710 8457   11
 2.00000+00 0.00000+00 6.60000-02 4.64866-03 0.00000+00 0.00000+002710 8457   12
 8.45000+02 0.00000+00 0.00000+00 0.00000+00 6.77300+02 2.03190+012710 8457   13
 7.04500+04 5.00000+01          0          0         12          02710 8457   14
 2.00000+00 0.00000+00 5.89500+00 4.94418-01 0.00000+00 0.00000+002710 8457   15
 1.32000+01 1.00000-01 8.30000+00 3.19376-01 3.76000+00 2.12424-012710 8457   16
 1.01750+05 5.00000+01          0          0         12          02710 8457   17
 2.00000+00 0.00000+00 4.35000-01 1.08931-01 0.00000+00 0.00000+002710 8457   18
 4.26000+00 4.00000-02 3.51000+00 1.59650-01 5.80000-01 7.21302-022710 8457   19
 1.15050+05 5.00000+01          0          0         12          02710 8457   20
 2.00000+00 0.00000+00 7.95000+00 5.30000-01 0.00000+00 0.00000+002710 8457   21
 2.57000-01 0.00000+00 2.11000-01 9.43763-03 3.55000-02 1.53109-032710 8457   22
 1.15650+05 5.00000+01          0          0         12          02710 8457   23
 2.00000+00 0.00000+00 4.65000+01 3.10000+00 0.00000+00 0.00000+002710 8457   24
 2.53000-01 0.00000+00 2.08000-01 9.37750-03 3.50000-02 1.52069-032710 8457   25
 1.42600+05 5.00000+01          0          0         12          02710 8457   26
 2.00000+00 0.00000+00 1.26000+00 1.23110-01 0.00000+00 0.00000+002710 8457   27
 1.47000+00 2.00000-02 1.12000+00 3.91019-02 2.65000-01 9.96005-032710 8457   28
 1.52230+05 9.00000+01          0          0         12          02710 8457   29
 2.00000+00 0.00000+00 1.80000-01 6.11882-02 0.00000+00 0.00000+002710 8457   30
 7.74000-01 0.00000+00 3.52000-01 1.52484-02 3.20000-01 1.38622-022710 8457   31
 1.55950+05 9.00000+01          0          0         12          02710 8457   32
 2.00000+00 0.00000+00 3.60000+00 3.00000-01 0.00000+00 0.00000+002710 8457   33
 1.11000+00 2.00000-02 8.50000-01 3.93732-02 1.99000-01 7.78723-032710 8457   34
 1.59100+05 1.00000+02          0          0         12          02710 8457   35
 2.00000+00 0.00000+00 1.20000-01 3.10483-02 0.00000+00 0.00000+002710 8457   36
 1.19000+00 0.00000+00 9.90000-01 4.22148-02 1.56000-01 6.84853-032710 8457   37
 1.72500+05 2.00000+02          0          0         12          02710 8457   38
 2.00000+00 0.00000+00 1.20000-01 3.10483-02 0.00000+00 0.00000+002710 8457   39
 1.60000+00 6.00000-01 7.91900-01 2.37570-02 1.23800-01 3.71400-032710 8457   40
 1.86200+05 0.00000+00          0          0         12          02710 8457   41
 2.00000+00 0.00000+00 1.50000+01 1.25000+00 0.00000+00 0.00000+002710 8457   42
 7.34000-02 0.00000+00 6.10000-02 2.63797-03 9.70000-03 4.17949-042710 8457   43
 1.86420+05 3.00000+01          0          0         12          02710 8457   44
 2.00000+00 0.00000+00 7.29000+00 4.86000-01 0.00000+00 0.00000+002710 8457   45
 7.10000-01 4.00000-03 5.74000-01 1.76785-02 1.05000-01 3.15000-032710 8457   46
 2.23230+05 3.00000+01          0          0         12          02710 8457   47
 2.00000+00 0.00000+00 2.05500+00 1.63918-01 0.00000+00 0.00000+002710 8457   48
 2.90000-01 4.00000-02 2.10000-01 4.04931-02 6.25000-02 1.94052-032710 8457   49
 2.24990+05 3.00000+01          0          0         12          02710 8457   50
 2.00000+00 0.00000+00 5.40000-01 8.31925-02 0.00000+00 0.00000+002710 8457   51
 2.40000-01 3.00000-02 1.60000-01 3.03816-02 6.11000-02 1.85739-032710 8457   52
 2.59250+05 2.00000+02          0          0         12          02710 8457   53
 2.00000+00 0.00000+00 8.55000-01 8.27587-02 0.00000+00 0.00000+002710 8457   54
 2.29000-01 2.10000-02 1.80000-01 2.07162-02 3.78000-02 1.28295-032710 8457   55
 2.71020+05 9.00000+01          0          0         12          02710 8457   56
 2.00000+00 0.00000+00 3.67500+00 2.72809-01 0.00000+00 0.00000+002710 8457   57
 2.84000-02 0.00000+00 2.37000-02 1.07029-03 3.64000-03 1.54999-042710 8457   58
 2.80800+05 9.00000+01          0          0         12          02710 8457   59
 2.00000+00 0.00000+00 8.10000-01 1.04957-01 0.00000+00 0.00000+002710 8457   60
 2.60000-02 0.00000+00 2.17000-02 9.55929-04 3.33000-03 1.41351-042710 8457   61
 3.04300+05 3.00000+02          0          0         12          02710 8457   62
 2.00000+00 0.00000+00 1.80000-01 6.11882-02 0.00000+00 0.00000+002710 8457   63
 2.14000-02 0.00000+00 1.79000-02 8.05214-04 2.72000-03 1.21485-042710 8457   64
 3.08250+05 9.00000+01          0          0         12          02710 8457   65
 2.00000+00 0.00000+00 8.55000-01 1.32850-01 0.00000+00 0.00000+002710 8457   66
 1.83000-01 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002710 8457   67
 3.11280+05 9.00000+01          0          0         12          02710 8457   68
 2.00000+00 0.00000+00 1.27500+00 1.59531-01 0.00000+00 0.00000+002710 8457   69
 2.03000-02 0.00000+00 1.70000-02 7.14213-04 2.57000-03 1.11105-042710 8457   70
 3.17750+05 9.00000+01          0          0         12          02710 8457   71
 2.00000+00 0.00000+00 5.25000-01 6.94622-02 0.00000+00 0.00000+002710 8457   72
 1.49000-01 2.00000-02 1.21000-01 1.93437-02 2.12000-02 1.35812-032710 8457   73
 3.67520+05 4.00000+01          0          0         12          02710 8457   74
 2.00000+00 0.00000+00 3.90000+00 3.43839-01 0.00000+00 0.00000+002710 8457   75
 1.20000-01 0.00000+00 1.00000-01 4.24264-03 1.55000-02 6.82807-042710 8457   76
 3.77350+05 5.00000+01          0          0         12          02710 8457   77
 2.00000+00 0.00000+00 4.27500+00 3.63112-01 0.00000+00 0.00000+002710 8457   78
 1.12000-01 0.00000+00 9.30000-02 4.09684-03 1.44000-02 6.60775-042710 8457   79
 3.82300+05 2.00000+02          0          0         12          02710 8457   80
 2.00000+00 0.00000+00 6.30000-01 6.15549-02 0.00000+00 0.00000+002710 8457   81
 1.08000-01 0.00000+00 9.00000-02 4.03609-03 1.39000-02 6.51068-042710 8457   82
 3.88800+05 1.00000+02          0          0         12          02710 8457   83
 2.00000+00 0.00000+00 1.56000+00 1.37535-01 0.00000+00 0.00000+002710 8457   84
 1.21000-02 0.00000+00 1.01000-02 4.26391-04 1.51000-03 6.74692-052710 8457   85
 4.17160+05 5.00000+01          0          0         12          02710 8457   86
 2.00000+00 0.00000+00 5.70000+00 4.84149-01 0.00000+00 0.00000+002710 8457   87
 3.24000-02 0.00000+00 2.41000-02 1.07830-03 6.35000-03 2.69054-042710 8457   88
 4.18350+05 1.00000+02          0          0         12          02710 8457   89
 2.00000+00 0.00000+00 8.10000-01 1.59424-01 0.00000+00 0.00000+002710 8457   90
 6.80000-02 1.40000-02 5.60000-02 1.21170-02 9.40000-03 1.23269-032710 8457   91
 4.26980+05 5.00000+01          0          0         12          02710 8457   92
 2.00000+00 0.00000+00 1.22700+01 9.88508-01 0.00000+00 0.00000+002710 8457   93
 8.09000-02 0.00000+00 6.75000-02 2.91730-03 1.04000-02 5.07291-042710 8457   94
 4.31450+05 1.00000+02          0          0         12          02710 8457   95
 2.00000+00 0.00000+00 7.05000-01 8.85099-02 0.00000+00 0.00000+002710 8457   96
 7.87000-02 0.00000+00 6.57000-02 2.80800-03 1.01000-02 4.26391-042710 8457   97
 4.50600+05 2.00000+02          0          0         12          02710 8457   98
 2.00000+00 0.00000+00 1.20000+00 8.54400-02 0.00000+00 0.00000+002710 8457   99
 7.03000-02 0.00000+00 5.87000-02 2.51816-03 9.00000-03 4.03609-042710 8457  100
 4.67500+05 3.00000+02          0          0         12          02710 8457  101
 2.00000+00 0.00000+00 6.60000-01 5.32541-02 0.00000+00 0.00000+002710 8457  102
 6.38000-02 0.00000+00 5.33000-02 2.26203-03 8.15000-03 3.49686-042710 8457  103
 4.73500+05 2.00000+02          0          0         12          02710 8457  104
 2.00000+00 0.00000+00 1.20000+00 8.54400-02 0.00000+00 0.00000+002710 8457  105
 6.17000-02 0.00000+00 5.16000-02 2.22628-03 7.88000-03 3.36875-042710 8457  106
 5.02400+05 3.00000+02          0          0         12          02710 8457  107
 2.00000+00 0.00000+00 7.50000-01 9.01388-02 0.00000+00 0.00000+002710 8457  108
 2.01000-02 0.00000+00 1.54000-02 6.80767-04 3.54000-03 1.52900-042710 8457  109
 5.04200+05 4.00000+02          0          0         12          02710 8457  110
 2.00000+00 0.00000+00 1.20000-01 3.10483-02 0.00000+00 0.00000+002710 8457  111
 5.27000-02 0.00000+00 4.38000-02 1.92005-03 6.69000-03 2.83338-042710 8457  112
 5.28500+05 2.00000+02          0          0         12          02710 8457  113
 2.00000+00 0.00000+00 2.20500+00 1.50030-01 0.00000+00 0.00000+002710 8457  114
 1.77000-02 0.00000+00 1.37000-02 6.47241-04 3.04000-03 1.35342-042710 8457  115
 5.63000+05 4.00000+02          0          0         12          02710 8457  116
 2.00000+00 0.00000+00 1.35000-01 3.13209-02 0.00000+00 0.00000+002710 8457  117
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 7.60484+05 4.00000+02          0          0          6          02710 8457  604
 2.00000+00 0.00000+00 1.19040-02 1.20761-03 0.00000+00 0.00000+002710 8457  605
 7.68784+05 3.00001+02          0          0          6          02710 8457  606
 2.00000+00 0.00000+00 4.80060-03 4.88806-04 0.00000+00 0.00000+002710 8457  607
 7.74219+05 4.00000+02          0          0          6          02710 8457  608
 2.00000+00 0.00000+00 2.03520-03 2.76050-04 0.00000+00 0.00000+002710 8457  609
 7.81919+05 4.00000+02          0          0          6          02710 8457  610
 2.00000+00 0.00000+00 1.11780-03 1.53402-04 0.00000+00 0.00000+002710 8457  611
 7.90984+05 3.00001+02          0          0          6          02710 8457  612
 2.00000+00 0.00000+00 7.28850-03 7.80413-04 0.00000+00 0.00000+002710 8457  613
 8.09784+05 4.00000+02          0          0          6          02710 8457  614
 2.00000+00 0.00000+00 1.20375-02 1.88493-03 0.00000+00 0.00000+002710 8457  615
 8.10319+05 6.00000+02          0          0          6          02710 8457  616
 2.00000+00 0.00000+00 1.99500-04 5.91726-05 0.00000+00 0.00000+002710 8457  617
 8.12784+05 4.00000+02          0          0          6          02710 8457  618
 2.00000+00 0.00000+00 1.19250-02 1.86832-03 0.00000+00 0.00000+002710 8457  619
 8.16219+05 4.00000+02          0          0          6          02710 8457  620
 2.00000+00 0.00000+00 1.78560-03 1.81142-04 0.00000+00 0.00000+002710 8457  621
 8.24519+05 3.00000+02          0          0          6          02710 8457  622
 2.00000+00 0.00000+00 8.41050-04 8.62308-05 0.00000+00 0.00000+002710 8457  623
 8.36084+05 3.00001+02          0          0          6          02710 8457  624
 2.00000+00 0.00000+00 6.30000-04 9.37514-05 0.00000+00 0.00000+002710 8457  625
 8.46719+05 3.00000+02          0          0          6          02710 8457  626
 2.00000+00 0.00000+00 1.09650-03 1.15404-04 0.00000+00 0.00000+002710 8457  627
 8.65519+05 4.00000+02          0          0          6          02710 8457  628
 2.00000+00 0.00000+00 1.81125-03 2.81104-04 0.00000+00 0.00000+002710 8457  629
 8.68519+05 4.00000+02          0          0          6          02710 8457  630
 2.00000+00 0.00000+00 1.80000-03 2.79428-04 0.00000+00 0.00000+002710 8457  631
 8.71784+05 3.00001+02          0          0          6          02710 8457  632
 2.00000+00 0.00000+00 1.14915-03 1.16963-04 0.00000+00 0.00000+002710 8457  633
 8.91819+05 3.00000+02          0          0          6          02710 8457  634
 2.00000+00 0.00000+00 9.00000-05 1.35208-05 0.00000+00 0.00000+002710 8457  635
 9.11384+05 3.00001+02          0          0          6          02710 8457  636
 2.00000+00 0.00000+00 2.57670-03 2.38203-04 0.00000+00 0.00000+002710 8457  637
 9.22784+05 3.00001+02          0          0          6          02710 8457  638
 2.00000+00 0.00000+00 1.11000-03 1.11475-04 0.00000+00 0.00000+002710 8457  639
 9.27519+05 3.00000+02          0          0          6          02710 8457  640
 2.00000+00 0.00000+00 1.62150-04 1.72437-05 0.00000+00 0.00000+002710 8457  641
 9.32584+05 3.00001+02          0          0          6          02710 8457  642
 2.00000+00 0.00000+00 7.17750-04 6.19588-05 0.00000+00 0.00000+002710 8457  643
 9.47484+05 3.00001+02          0          0          6          02710 8457  644
 2.00000+00 0.00000+00 6.28155-03 5.25929-04 0.00000+00 0.00000+002710 8457  645
 9.67118+05 3.00000+02          0          0          6          02710 8457  646
 2.00000+00 0.00000+00 3.84300-04 3.58183-05 0.00000+00 0.00000+002710 8457  647
 9.68984+05 3.00001+02          0          0          6          02710 8457  648
 2.00000+00 0.00000+00 6.76275-02 5.51970-03 0.00000+00 0.00000+002710 8457  649
 9.78484+05 3.00001+02          0          0          6          02710 8457  650
 2.00000+00 0.00000+00 5.22600-04 5.76110-05 0.00000+00 0.00000+002710 8457  651
 9.78519+05 3.00000+02          0          0          6          02710 8457  652
 2.00000+00 0.00000+00 1.57500-04 1.66772-05 0.00000+00 0.00000+002710 8457  653
 9.88319+05 3.00000+02          0          0          6          02710 8457  654
 2.00000+00 0.00000+00 9.90000-05 9.26733-06 0.00000+00 0.00000+002710 8457  655
 9.88384+05 3.00001+02          0          0          6          02710 8457  656
 2.00000+00 0.00000+00 7.92000-04 8.63524-05 0.00000+00 0.00000+002710 8457  657
 9.99484+05 3.00001+02          0          0          6          02710 8457  658
 2.00000+00 0.00000+00 1.64160-02 2.38480-03 0.00000+00 0.00000+002710 8457  659
 1.00322+06 3.00000+02          0          0          6          02710 8457  660
 2.00000+00 0.00000+00 8.91000-04 8.09417-05 0.00000+00 0.00000+002710 8457  661
 1.02472+06 3.00000+02          0          0          6          02710 8457  662
 2.00000+00 0.00000+00 1.00965-02 8.52276-04 0.00000+00 0.00000+002710 8457  663
 1.03422+06 3.00000+02          0          0          6          02710 8457  664
 2.00000+00 0.00000+00 7.41000-05 8.77755-06 0.00000+00 0.00000+002710 8457  665
 1.03628+06 4.00000+02          0          0          6          02710 8457  666
 2.00000+00 0.00000+00 1.55295-03 2.20490-04 0.00000+00 0.00000+002710 8457  667
 1.04412+06 3.00000+02          0          0          6          02710 8457  668
 2.00000+00 0.00000+00 1.08000-04 1.28042-05 0.00000+00 0.00000+002710 8457  669
 1.04778+06 4.00000+02          0          0          6          02710 8457  670
 2.00000+00 0.00000+00 7.11600-04 2.72730-04 0.00000+00 0.00000+002710 8457  671
 1.05522+06 3.00000+02          0          0          6          02710 8457  672
 2.00000+00 0.00000+00 2.47680-03 3.22693-04 0.00000+00 0.00000+002710 8457  673
 1.07308+06 3.00001+02          0          0          6          02710 8457  674
 2.00000+00 0.00000+00 4.13070-03 3.67735-04 0.00000+00 0.00000+002710 8457  675
 1.09202+06 4.00000+02          0          0          6          02710 8457  676
 2.00000+00 0.00000+00 2.32050-04 3.30393-05 0.00000+00 0.00000+002710 8457  677
 1.10352+06 4.00000+02          0          0          6          02710 8457  678
 2.00000+00 0.00000+00 1.05600-04 4.05058-05 0.00000+00 0.00000+002710 8457  679
 1.11508+06 3.00001+02          0          0          6          02710 8457  680
 2.00000+00 0.00000+00 3.69150-03 3.13550-04 0.00000+00 0.00000+002710 8457  681
 1.12882+06 3.00000+02          0          0          6          02710 8457  682
 2.00000+00 0.00000+00 6.17400-04 5.62001-05 0.00000+00 0.00000+002710 8457  683
 1.17082+06 3.00000+02          0          0          6          02710 8457  684
 2.00000+00 0.00000+00 5.17500-04 5.24222-05 0.00000+00 0.00000+002710 8457  685
 1.18628+06 4.00000+02          0          0          6          02710 8457  686
 2.00000+00 0.00000+00 1.41750-03 1.96114-04 0.00000+00 0.00000+002710 8457  687
 1.19228+06 4.00000+02          0          0          6          02710 8457  688
 2.00000+00 0.00000+00 5.28000-04 7.82827-05 0.00000+00 0.00000+002710 8457  689
 1.22268+06 5.00000+02          0          0          6          02710 8457  690
 2.00000+00 0.00000+00 1.30200-04 3.41722-05 0.00000+00 0.00000+002710 8457  691
 1.23438+06 4.00000+02          0          0          6          02710 8457  692
 2.00000+00 0.00000+00 4.79250-04 4.99638-05 0.00000+00 0.00000+002710 8457  693
 1.24202+06 4.00000+02          0          0          6          02710 8457  694
 2.00000+00 0.00000+00 2.24100-04 3.05610-05 0.00000+00 0.00000+002710 8457  695
 1.24802+06 4.00000+02          0          0          6          02710 8457  696
 2.00000+00 0.00000+00 7.80000-05 1.15472-05 0.00000+00 0.00000+002710 8457  697
 1.25938+06 3.00001+02          0          0          6          02710 8457  698
 2.00000+00 0.00000+00 1.92060-03 1.91811-04 0.00000+00 0.00000+002710 8457  699
 1.27842+06 5.00000+02          0          0          6          02710 8457  700
 2.00000+00 0.00000+00 2.04000-05 5.34735-06 0.00000+00 0.00000+002710 8457  701
 1.29008+06 4.00000+02          0          0          6          02710 8457  702
 2.00000+00 0.00000+00 6.05550-04 7.29362-05 0.00000+00 0.00000+002710 8457  703
 1.29012+06 4.00000+02          0          0          6          02710 8457  704
 2.00000+00 0.00000+00 7.42500-05 7.68305-06 0.00000+00 0.00000+002710 8457  705
 1.31512+06 3.00000+02          0          0          6          02710 8457  706
 2.00000+00 0.00000+00 2.87100-04 2.90051-05 0.00000+00 0.00000+002710 8457  707
 1.33868+06 3.00001+02          0          0          6          02710 8457  708
 2.00000+00 0.00000+00 4.71750-04 6.71099-05 0.00000+00 0.00000+002710 8457  709
 1.34582+06 4.00000+02          0          0          6          02710 8457  710
 2.00000+00 0.00000+00 8.91000-05 1.09054-05 0.00000+00 0.00000+002710 8457  711
 1.39442+06 3.00000+02          0          0          6          02710 8457  712
 2.00000+00 0.00000+00 7.14000-05 1.02131-05 0.00000+00 0.00000+002710 8457  713
 0.00000+00 9.00000+00          0          0          6          52710 8457  714
 1.00000-02 0.00000+00 9.47070+04 2.20960+03 0.00000+00 0.00000+002710 8457  715
 8.15000+03 0.00000+00          0          0          6          02710 8457  716
 2.00000+00 0.00000+00 6.03046+01 6.88502+00 0.00000+00 0.00000+002710 8457  717
 5.62770+04 1.00000+00          0          0          6          02710 8457  718
 2.00000+00 0.00000+00 4.26878+01 1.71671+00 0.00000+00 0.00000+002710 8457  719
 5.75320+04 1.00000+00          0          0          6          02710 8457  720
 2.00000+00 0.00000+00 7.44988+01 2.88362+00 0.00000+00 0.00000+002710 8457  721
 6.52000+04 0.00000+00          0          0          6          02710 8457  722
 2.00000+00 0.00000+00 3.14060+01 1.30604+00 0.00000+00 0.00000+002710 8457  723
 5.10999+05 1.50000-01          0          0          6          02710 8457  724
 2.00000+00 0.00000+00 4.75800-01 7.74597-02 0.00000+00 0.00000+002710 8457  725
                                                                  2710 8  099999
                                                                  2710 0  0    0
                                                                     0 0  0    0
 7.417800+4 1.764170+2         -1          0          2          12711 1451    1
 0.000000+0 1.000000+0          0          0          0          62711 1451    2
 0.000000+0 0.000000+0          0          0          4        3112711 1451    3
 0.000000+0 0.000000+0          0          0         31          22711 1451    4
 74-W -178 HAR+WIN    EVAL-SEP94 A.L. NICHOLS                     2711 1451    5
                      DIST-NOV07                       261107     2711 1451    6
----JEFF-311          MATERIAL 2711                               2711 1451    7
-----RADIOACTIVE DECAY DATA                                       2711 1451    8
------ENDF-6 FORMAT                                               2711 1451    9
******************************************************************2711 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2711 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2711 1451   12
**             Original data taken from:  UKPADD67              **2711 1451   13
******************************************************************2711 1451   14
          E BROWNE              NUCL DATA SHEETS 72 (1994) 221    2711 1451   15
          E BROWNE              NUCL DATA SHEETS 54 (1988) 199    2711 1451   16
          G WILKINSON           PHYS REV 80 (1950) 495            2711 1451   17
          C L RAO, L YAFFE      CAN J CHEM 41 (1963) 2516:        2711 1451   18
                                                 HALF-LIFE        2711 1451   19
          A SANTONI, J VALENTIN    PHYS NUCL ANNUAIRE 1962-63,    2711 1451   20
                                   FACULTE SCI L'UNIV PARIS INST  2711 1451   21
                                   RAD (1964) 40:HALF-LIFE        2711 1451   22
          H L NIELSEN ET AL     NUCL PHYS A93 (1967) 385          2711 1451   23
                                                                  2711 1451   24
                                                                  2711 1451   25
      BETA+ + NEUTRINO ENERGY        =     91.3000  KEV           2711 1451   26
      MEAN X-RAY ENERGY              =     19.1625  KEV           2711 1451   27
      MEAN AUGER ELECTRON ENERGY     =      6.9949  KEV           2711 1451   28
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.0013  KEV           2711 1451   29
      EFFECTIVE Q VALUE              =     91.3000  KEV           2711 1451   30
      UNCERTAINTY IN EFFECTIVE Q (%) =      2.1906                2711 1451   31
      CALCULATED Q VALUE             =     90.1249  KEV           2711 1451   32
      % DEVIATION                    =      1.2871                2711 1451   33
                                                                  2711 1451   34
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2711 1451   35
                                1        451         37          12711 1451   36
                                8        457         31          12711 1451   37
 0.000000+0 0.000000+0          0          0          0          02711 1  099999
                                                                  2711 0  0    0
7.41780E+041.76417E+02          0          0          0          32711 8457    1
1.86624E+062.59200E+04          0          0          6          02711 8457    2
6.99493E+036.99493E+021.91637E+041.91625E+030.00000E+000.00000E+002711 8457    3
0.00000E+00 1.0000E+00          0          0          6          12711 8457    4
2.00000E+000.00000E+009.13000E+042.00000E+031.00000E+000.00000E+002711 8457    5
0.00000E+002.00000E+00          0          0          6          12711 8457    6
1.00000E+001.00000E-040.00000E+000.00000E+000.00000E+000.00000E+002711 8457    7
9.13000E+042.00000E+03          0          0          6          02711 8457    8
2.00000E+001.00000E+001.00000E+000.00000E+000.00000E+000.00000E+002711 8457    9
0.00000E+008.00000E+00          0          0          6          32711 8457   10
1.00000E+000.00000E+006.99493E+036.99493E+020.00000E+000.00000E+002711 8457   11
2.18000E+031.09000E+02          0          0          6          02711 8457   12
2.00000E+000.00000E+001.25857E+001.25857E-010.00000E+000.00000E+002711 8457   13
6.35300E+033.17650E+02          0          0          6          02711 8457   14
2.00000E+000.00000E+005.63749E-015.63749E-020.00000E+000.00000E+002711 8457   15
4.96530E+042.48265E+03          0          0          6          02711 8457   16
2.00000E+000.00000E+001.34886E-021.34886E-030.00000E+000.00000E+002711 8457   17
0.00000E+009.00000E+00          0          0          6          62711 8457   18
1.00000E+000.00000E+001.91625E+041.91625E+030.00000E+000.00000E+002711 8457   19
2.18000E+034.36000E+01          0          0          6          02711 8457   20
2.00000E+000.00000E+002.15053E-022.15053E-030.00000E+000.00000E+002711 8457   21
8.33100E+031.66620E+02          0          0          6          02711 8457   22
2.00000E+000.00000E+002.23610E-012.23610E-020.00000E+000.00000E+002711 8457   23
5.62770E+041.12554E+03          0          0          6          02711 8457   24
2.00000E+000.00000E+008.42795E-028.42795E-030.00000E+000.00000E+002711 8457   25
5.75320E+041.15064E+03          0          0          6          02711 8457   26
2.00000E+000.00000E+001.46828E-011.46828E-020.00000E+000.00000E+002711 8457   27
6.52000E+041.30400E+03          0          0          6          02711 8457   28
2.00000E+000.00000E+004.94811E-024.94811E-030.00000E+000.00000E+002711 8457   29
6.70000E+041.34000E+03          0          0          6          02711 8457   30
2.00000E+000.00000E+001.24804E-021.24804E-030.00000E+000.00000E+002711 8457   31
                                                                  2711 8  099999
                                                                  2711 0  0    0
                                                                     0 0  0    0
 7.417900+4 1.774100+2         -1          0          2          12712 1451    1
 0.000000+0 1.000000+0          0          0          0          62712 1451    2
 0.000000+0 0.000000+0          0          0          4        3112712 1451    3
 0.000000+0 0.000000+0          0          0         47          22712 1451    4
 74-W -179 ENSDF      EVAL-MAY00 CONVERSION OF ENSDF              2712 1451    5
 /ENSDF/              DIST-NOV07                       261107     2712 1451    6
----JEFF-311          MATERIAL 2712                               2712 1451    7
-----RADIOACTIVE DECAY DATA                                       2712 1451    8
------ENDF-6 FORMAT                                               2712 1451    9
******************************************************************2712 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2712 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2712 1451   12
**             Original data taken from:  ENSDF                 **2712 1451   13
******************************************************************2712 1451   14
******************************************************************2712 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2712 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2712 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2712 1451   18
******************************************************************2712 1451   19
179W  DECAY 37.05 M   16                    I(min) = 0.0E+00 %    2712 1451   20
         Ex = 0.0         keV                     1 decay mode(s) 2712 1451   21
                                                                  2712 1451   22
179W EC DECAY               Q =  1060.0000 keV      16.0000       2712 1451   23
         Branching                100.0000 %         0.0000       2712 1451   24
                         Br*Q =  1060.0000 keV      16.0000       2712 1451   25
                                              0 isomeric state(s) 2712 1451   26
                                                                  2712 1451   27
Individual beta+ transitions                                      2712 1451   28
Final level    end point    shape    av.energy        intensity   2712 1451   29
   30.700      7.302  16.000  0      0.000   0.000    0.000 0.000 2712 1451   30
    0.000     38.002  16.000  0      0.000   0.000    0.000 0.000 2712 1451   31
                                                                  2712 1451   32
         Mean alpha    energy       0.0000 keV       0.0000       2712 1451   33
         Mean beta     energy       0.0000 keV       0.0000       2712 1451   34
         Mean conv. e- energy       6.3749 keV       0.8344       2712 1451   35
         Mean Auger e- energy       6.5040 keV       0.7840       2712 1451   36
         Mean gamma    energy       5.6682 keV                    2712 1451   37
         Mean X        energy      48.3800 keV       0.7216       2712 1451   38
         Mean recoil   energy       0.0000 keV       0.0000       2712 1451   39
         Mean neutrino energy     977.4084 keV      16.6992       2712 1451   40
         Mean neutron  energy       0.0000 keV       0.0000       2712 1451   41
         Total         energy    1044.3354 keV      16.7793       2712 1451   42
         Q effective             1060.0000 keV      16.0000       2712 1451   43
         diff. mode               -15.6646 keV      -1.4778 %     2712 1451   44
                                                                  2712 1451   45
         Mean e- bind. energy      59.9424 keV                    2712 1451   46
         diff. atomic              -5.0585 keV      -8.4389 %     2712 1451   47
         diff. nuclear            -10.6061 keV      -1.0006 %     2712 1451   48
                                                                  2712 1451   49
         B+ fraction                0.0000 %         0.0000       2712 1451   50
                                                                  2712 1451   51
                                1        451         53          02712 1451   52
                                8        457         49          02712 1451   53
 0.000000+0 0.000000+0          0          0          0          02712 1  099999
                                                                  2712 0  0    0
 7.41790+04 1.77410+02          0          0          0          42712 8457    1
 2.22300+03 9.60000+00          0          0          6          02712 8457    2
 1.28789+04 1.14494+03 5.40482+04 1.17052+03 0.00000+00 0.00000+002712 8457    3
 3.50000+00-1.00000+00          0          0          6          12712 8457    4
 2.00000+00 0.00000+00 1.06000+06 1.60000+04 1.00000+00 0.00000+002712 8457    5
 0.00000+00 0.00000+00          0          0          6          22712 8457    6
 1.00000-02 0.00000+00 5.66820+03 9.21594+02 0.00000+00 0.00000+002712 8457    7
 3.07000+04 1.00000+02          0          0         12          02712 8457    8
 2.00000+00 0.00000+00 1.80000+01 3.00000+00 0.00000+00 0.00000+002712 8457    9
 4.60000+00 9.00000-01 0.00000+00 0.00000+00 1.35800+00 4.24705-022712 8457   10
 1.33900+05 2.00000+02          0          0         12          02712 8457   11
 2.00000+00 0.00000+00 1.06200-01 2.07348-02 0.00000+00 0.00000+002712 8457   12
 1.60000+00 4.00000-01 1.10000+00 6.00907-01 4.10000-01 1.60472-012712 8457   13
 0.00000+00 2.00000+00          0          0          6          32712 8457   14
 1.00000-02 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002712 8457   15
 9.26100+05 1.60012+04          0          0          6          02712 8457   16
 2.00000+00 1.00000+00 2.80000-01 7.00000-02 0.00000+00 0.00000+002712 8457   17
 1.02930+06 1.60003+04          0          0          6          02712 8457   18
 2.00000+00 1.00000+00 9.92000+01 5.00000-01 0.00000+00 0.00000+002712 8457   19
 1.06000+06 1.60000+04          0          0          6          02712 8457   20
 2.00000+00 1.00000+00 1.00000+00 0.00000+00 0.00000+00 0.00000+002712 8457   21
 0.00000+00 8.00000+00          0          0          6          82712 8457   22
 1.00000-02 0.00000+00 1.28789+04 1.14494+03 0.00000+00 0.00000+002712 8457   23
 6.35000+03 0.00000+00          0          0          6          02712 8457   24
 2.00000+00 0.00000+00 7.62458+01 4.96087+00 0.00000+00 0.00000+002712 8457   25
 1.90185+04 1.00000+02          0          0          6          02712 8457   26
 2.00000+00 0.00000+00 2.44440+01 4.14510+00 0.00000+00 0.00000+002712 8457   27
 2.79920+04 1.00001+02          0          0          6          02712 8457   28
 2.00000+00 0.00000+00 5.63400+00 9.55617-01 0.00000+00 0.00000+002712 8457   29
 4.62000+04 0.00000+00          0          0          6          02712 8457   30
 2.00000+00 0.00000+00 3.59822+00 1.55388+00 0.00000+00 0.00000+002712 8457   31
 6.64836+04 2.00001+02          0          0          6          02712 8457   32
 2.00000+00 0.00000+00 1.16820-01 6.77697-02 0.00000+00 0.00000+002712 8457   33
 1.22219+05 2.00000+02          0          0          6          02712 8457   34
 2.00000+00 0.00000+00 4.35420-02 1.90448-02 0.00000+00 0.00000+002712 8457   35
 1.31192+05 2.00000+02          0          0          6          02712 8457   36
 2.00000+00 0.00000+00 1.06200-02 5.70937-03 0.00000+00 0.00000+002712 8457   37
 1.33335+05 2.00001+02          0          0          6          02712 8457   38
 2.00000+00 0.00000+00 3.07980-03 1.41216-03 0.00000+00 0.00000+002712 8457   39
 0.00000+00 9.00000+00          0          0          6          42712 8457   40
 1.00000-02 0.00000+00 4.83800+04 7.21648+02 0.00000+00 0.00000+002712 8457   41
 8.15000+03 0.00000+00          0          0          6          02712 8457   42
 2.00000+00 0.00000+00 2.96512+01 3.50547+00 0.00000+00 0.00000+002712 8457   43
 5.62770+04 1.00000+00          0          0          6          02712 8457   44
 2.00000+00 0.00000+00 2.24595+01 5.59461-01 0.00000+00 0.00000+002712 8457   45
 5.75320+04 1.00000+00          0          0          6          02712 8457   46
 2.00000+00 0.00000+00 3.91963+01 8.77718-01 0.00000+00 0.00000+002712 8457   47
 6.52000+04 0.00000+00          0          0          6          02712 8457   48
 2.00000+00 0.00000+00 1.65237+01 4.47240-01 0.00000+00 0.00000+002712 8457   49
                                                                  2712 8  099999
                                                                  2712 0  0    0
                                                                     0 0  0    0
 7.417900+4 1.774100+2         -1          0          2          12713 1451    1
 2.219260+5 1.000000+0          1          1          0          62713 1451    2
 0.000000+0 0.000000+0          0          0          4        3112713 1451    3
 0.000000+0 0.000000+0          0          0         18          22713 1451    4
 74-W -179MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2713 1451    5
                      DIST-NOV07                       261107     2713 1451    6
----JEFF-311          MATERIAL 2713                               2713 1451    7
-----RADIOACTIVE DECAY DATA                                       2713 1451    8
------ENDF-6 FORMAT                                               2713 1451    9
******************************************************************2713 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2713 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2713 1451   12
**             Original data taken from:  NUBASE                **2713 1451   13
******************************************************************2713 1451   14
******************************************************************2713 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2713 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2713 1451   17
                                                                  2713 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2713 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2713 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2713 1451   21
******************************************************************2713 1451   22
                                1        451         24          02713 1451   23
                                8        457          6          02713 1451   24
 0.000000+0 0.000000+0          0          0          0          02713 1  099999
                                                                  2713 0  0    0
 7.41790+04 1.77410+02          1          1          0          02713 8457    1
 3.84000+02 4.20000+00          0          0          6          02713 8457    2
 1.19861+03 0.00000+00 2.22503+05 0.00000+00 0.00000+00 0.00000+002713 8457    3
 5.00000-01-1.00000+00          0          0         12          22713 8457    4
 3.00000+00 0.00000+00 2.21926+05 0.00000+00 9.97200-01 0.00000+002713 8457    5
 2.00000+00 0.00000+00 1.28423+06 0.00000+00 2.80000-03 0.00000+002713 8457    6
                                                                  2713 8  099999
                                                                  2713 0  0    0
                                                                     0 0  0    0
 7.418000+4 1.784010+2         -1          0          2          12714 1451    1
 0.000000+0 0.000000+0          0          0          0          62714 1451    2
 0.000000+0 0.000000+0          0          0          4        3112714 1451    3
 0.000000+0 0.000000+0          0          0         22          22714 1451    4
 74-W -180 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2714 1451    5
                      DIST-NOV07                       261107     2714 1451    6
----JEFF-311          MATERIAL 2714                               2714 1451    7
-----RADIOACTIVE DECAY DATA                                       2714 1451    8
------ENDF-6 FORMAT                                               2714 1451    9
******************************************************************2714 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2714 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2714 1451   12
**             Original data taken from:  NUBASE                **2714 1451   13
******************************************************************2714 1451   14
******************************************************************2714 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2714 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2714 1451   17
                                                                  2714 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2714 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2714 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2714 1451   21
******************************************************************2714 1451   22
STABLE NUCLEUS                                                    2714 1451   23
       SPIN          0.0                                          2714 1451   24
       PARITY        1.0                                          2714 1451   25
NATURAL ABUNDANCE    0.12 1      %                                2714 1451   26
                                1        451         28          02714 1451   27
                                8        457          5          02714 1451   28
 0.000000+0 0.000000+0          0          0          0          02714 1  099999
                                                                  2714 0  0    0
 7.41800+04 1.78401+02          0          0          1          02714 8457    1
 0.00000+00 0.00000+00          0          0          6          02714 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002714 8457    3
 0.00000+00 1.00000+00          0          0          6          02714 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002714 8457    5
                                                                  2714 8  099999
                                                                  2714 0  0    0
                                                                     0 0  0    0
 7.418000+4 1.784010+2         -1          0          2          12715 1451    1
 1.529010+6 1.000000+0          1          1          0          62715 1451    2
 0.000000+0 0.000000+0          0          0          4        3112715 1451    3
 0.000000+0 0.000000+0          0          0         18          22715 1451    4
 74-W -180MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2715 1451    5
                      DIST-NOV07                       261107     2715 1451    6
----JEFF-311          MATERIAL 2715                               2715 1451    7
-----RADIOACTIVE DECAY DATA                                       2715 1451    8
------ENDF-6 FORMAT                                               2715 1451    9
******************************************************************2715 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2715 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2715 1451   12
**             Original data taken from:  NUBASE                **2715 1451   13
******************************************************************2715 1451   14
******************************************************************2715 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2715 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2715 1451   17
                                                                  2715 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2715 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2715 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2715 1451   21
******************************************************************2715 1451   22
                                1        451         24          02715 1451   23
                                8        457          5          02715 1451   24
 0.000000+0 0.000000+0          0          0          0          02715 1  099999
                                                                  2715 0  0    0
 7.41800+04 1.78401+02          1          1          0          02715 8457    1
 5.47000-03 9.00000-05          0          0          6          02715 8457    2
 0.00000+00 0.00000+00 1.52901+06 0.00000+00 0.00000+00 0.00000+002715 8457    3
 8.00000+00-1.00000+00          0          0          6          12715 8457    4
 3.00000+00 0.00000+00 1.52901+06 0.00000+00 1.00000+00 0.00000+002715 8457    5
                                                                  2715 8  099999
                                                                  2715 0  0    0
                                                                     0 0  0    0
 7.418100+4 1.793940+2         -1          0          2          12716 1451    1
 0.000000+0 1.000000+0          0          0          0          62716 1451    2
 0.000000+0 0.000000+0          0          0          4        3112716 1451    3
 0.000000+0 0.000000+0          0          0         41          22716 1451    4
 74-W -181 HAR+WIN    EVAL-AUG91 A.L. NICHOLS                     2716 1451    5
                      DIST-NOV07                       261107     2716 1451    6
----JEFF-311          MATERIAL 2716                               2716 1451    7
-----RADIOACTIVE DECAY DATA                                       2716 1451    8
------ENDF-6 FORMAT                                               2716 1451    9
******************************************************************2716 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2716 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2716 1451   12
**             Original data taken from:  UKPADD67              **2716 1451   13
******************************************************************2716 1451   14
      R.B.FIRESTONE                 NUCL DATA SHEETS 43(1984)289  2716 1451   15
      J.F.EMERY ET AL         NUCL SCI ENG 48(1972)319:HALF-LIFE  2716 1451   16
      H.BLUMBERG ET AL              NUCL PHYS A136(1969)624       2716 1451   17
      W.A.MYERS, R.J.NAGLE    J INORG NUCL CHEM 35(1971)3985      2716 1451   18
      I.P.KOCHERY             PHD THESIS, EMORY UNIV (1978)       2716 1451   19
      P.A.INDIRA ET AL              Z PHYSIK  A290(1979)245       2716 1451   20
                                                                  2716 1451   21
          THE DECAY SCHEME PROVED DIFFICULT TO ESTABLISH ON THE   2716 1451   22
      BASIS OF THE PUBLISHED DATA.  ABSOLUTE GAMMA-RAY EMISSION   2716 1451   23
      PROBABILITIES WERE ADOPTED FROM THE MEASUREMENTS OF INDIRA  2716 1451   24
      ET AL.  A MAJOR DIFFICULTY CAN BE IDENTIFIED WITH THE E1    2716 1451   25
      6.24 KEV GAMMA-RAY TRANSITION AND ILL-DEFINED INTERNAL      2716 1451   26
      CONVERSION COEFFICIENTS; AN ANOMALOUS VALUE OF 71 HAS BEEN  2716 1451   27
      USED (BLUMBERG ET AL) TO GIVE EC TRANSITION PROBABILITIES   2716 1451   28
      OF 0.75 AND 0.25 TO THE 6.24 AND 0 KEV NUCLEAR LEVELS       2716 1451   29
      RESPECTIVELY.  FURTHER STUDIES ARE REQUIRED TO DETERMINE    2716 1451   30
      THE DECAY SCHEME WITH GREATER CONFIDENCE.                   2716 1451   31
                                                                  2716 1451   32
                                                                  2716 1451   33
      MEAN GAMMA ENERGY              =      0.2323  KEV           2716 1451   34
      BETA+ + NEUTRINO ENERGY        =    181.5916  KEV           2716 1451   35
      MEAN X-RAY ENERGY              =     40.9685  KEV           2716 1451   36
      MEAN AUGER ELECTRON ENERGY     =      9.5408  KEV           2716 1451   37
      MEAN CONVERSION ELECTRON ENERGY=      3.1408  KEV           2716 1451   38
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.0049  KEV           2716 1451   39
      EFFECTIVE Q VALUE              =    186.0000  KEV           2716 1451   40
      UNCERTAINTY IN EFFECTIVE Q (%) =      3.7634                2716 1451   41
      CALCULATED Q VALUE             =    185.8728  KEV           2716 1451   42
      % DEVIATION                    =      0.0684                2716 1451   43
                                                                  2716 1451   44
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2716 1451   45
                                1        451         47          12716 1451   46
                                8        457         62          12716 1451   47
 0.000000+0 0.000000+0          0          0          0          02716 1  099999
                                                                  2716 0  0    0
7.41810E+041.79394E+02          0          0          0          42716 8457    1
1.04527E+071.03680E+04          0          0          6          02716 8457    2
1.26815E+041.00444E+034.12058E+044.09686E+030.00000E+000.00000E+002716 8457    3
4.50000E+00 1.0000E+00          0          0          6          12716 8457    4
2.00000E+000.00000E+001.86000E+057.00000E+031.00000E+000.00000E+002716 8457    5
0.00000E+000.00000E+00          0          0          6          32716 8457    6
1.04000E-020.00000E+002.32303E+025.12679E+000.00000E+000.00000E+002716 8457    7
6.24000E+032.00000E+01          0          0         12          02716 8457    8
2.00000E+000.00000E+001.00000E+002.88462E-020.00000E+000.00000E+002716 8457    9
7.10000E+011.98800E+000.00000E+000.00000E+000.00000E+000.00000E+002716 8457   10
1.36260E+052.00000E+01          0          0         12          02716 8457   11
2.00000E+000.00000E+003.00000E-029.61539E-040.00000E+000.00000E+002716 8457   12
1.76000E+004.92800E-021.39000E+003.89200E-022.80000E-017.84000E-032716 8457   13
1.52310E+054.00000E+01          0          0         12          02716 8457   14
2.00000E+000.00000E+007.88462E-022.88462E-030.00000E+000.00000E+002716 8457   15
1.23000E+005.04300E-029.70000E-013.97700E-022.10000E-018.61000E-032716 8457   16
0.00000E+002.00000E+00          0          0          6          42716 8457   17
1.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002716 8457   18
2.70000E+047.00000E+03          0          0          6          02716 8457   19
2.00000E+001.00000E+001.80000E-031.00000E-040.00000E+000.00000E+002716 8457   20
5.00000E+047.00000E+03          0          0          6          02716 8457   21
2.00000E+001.00000E+008.60000E-044.00000E-050.00000E+000.00000E+002716 8457   22
1.80000E+057.00000E+03          0          0          6          02716 8457   23
2.00000E+001.00000E+007.50000E-012.00000E-020.00000E+000.00000E+002716 8457   24
1.86000E+057.00000E+03          0          0          6          02716 8457   25
2.00000E+001.00000E+002.50000E-012.00000E-020.00000E+000.00000E+002716 8457   26
0.00000E+008.00000E+00          0          0          6         102716 8457   27
1.00000E+000.00000E+001.26815E+041.26815E+030.00000E+000.00000E+002716 8457   28
2.18000E+031.09000E+02          0          0          6          02716 8457   29
2.00000E+000.00000E+001.99251E+001.99251E-010.00000E+000.00000E+002716 8457   30
4.06000E+032.03000E+02          0          0          6          02716 8457   31
2.00000E+000.00000E+007.38400E-017.38400E-020.00000E+000.00000E+002716 8457   32
6.35300E+033.17650E+02          0          0          6          02716 8457   33
2.00000E+000.00000E+005.79876E-015.79876E-020.00000E+000.00000E+002716 8457   34
4.96530E+042.48265E+03          0          0          6          02716 8457   35
2.00000E+000.00000E+003.04741E-023.04741E-030.00000E+000.00000E+002716 8457   36
6.88436E+043.44218E+03          0          0          6          02716 8457   37
2.00000E+000.00000E+004.33680E-044.33680E-050.00000E+000.00000E+002716 8457   38
8.48936E+044.24468E+03          0          0          6          02716 8457   39
2.00000E+000.00000E+007.95400E-047.95400E-050.00000E+000.00000E+002716 8457   40
1.26379E+056.31894E+03          0          0          6          02716 8457   41
2.00000E+000.00000E+008.73600E-058.73600E-060.00000E+000.00000E+002716 8457   42
1.34080E+056.70400E+03          0          0          6          02716 8457   43
2.00000E+000.00000E+002.80800E-052.80800E-060.00000E+000.00000E+002716 8457   44
1.42429E+057.12145E+03          0          0          6          02716 8457   45
2.00000E+000.00000E+001.72200E-041.72200E-050.00000E+000.00000E+002716 8457   46
1.50130E+057.50650E+03          0          0          6          02716 8457   47
2.00000E+000.00000E+004.10000E-054.10000E-060.00000E+000.00000E+002716 8457   48
0.00000E+009.00000E+00          0          0          6          62716 8457   49
1.00000E+000.00000E+004.09685E+044.09685E+030.00000E+000.00000E+002716 8457   50
2.18000E+034.36000E+01          0          0          6          02716 8457   51
2.00000E+000.00000E+003.40462E-023.40462E-030.00000E+000.00000E+002716 8457   52
8.33100E+031.66620E+02          0          0          6          02716 8457   53
2.00000E+000.00000E+002.30007E-012.30007E-020.00000E+000.00000E+002716 8457   54
5.62770E+041.12554E+03          0          0          6          02716 8457   55
2.00000E+000.00000E+001.90408E-011.90408E-020.00000E+000.00000E+002716 8457   56
5.75320E+041.15064E+03          0          0          6          02716 8457   57
2.00000E+000.00000E+003.31722E-013.31722E-020.00000E+000.00000E+002716 8457   58
6.52000E+041.30400E+03          0          0          6          02716 8457   59
2.00000E+000.00000E+001.11790E-011.11790E-020.00000E+000.00000E+002716 8457   60
6.70000E+041.34000E+03          0          0          6          02716 8457   61
2.00000E+000.00000E+002.81964E-022.81964E-030.00000E+000.00000E+002716 8457   62
                                                                  2716 8  099999
                                                                  2716 0  0    0
                                                                     0 0  0    0
 7.418200+4 1.803850+2         -1          0          2          12717 1451    1
 0.000000+0 0.000000+0          0          0          0          62717 1451    2
 0.000000+0 0.000000+0          0          0          4        3112717 1451    3
 0.000000+0 0.000000+0          0          0         22          22717 1451    4
 74-W -182 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2717 1451    5
                      DIST-NOV07                       261107     2717 1451    6
----JEFF-311          MATERIAL 2717                               2717 1451    7
-----RADIOACTIVE DECAY DATA                                       2717 1451    8
------ENDF-6 FORMAT                                               2717 1451    9
******************************************************************2717 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2717 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2717 1451   12
**             Original data taken from:  NUBASE                **2717 1451   13
******************************************************************2717 1451   14
******************************************************************2717 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2717 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2717 1451   17
                                                                  2717 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2717 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2717 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2717 1451   21
******************************************************************2717 1451   22
STABLE NUCLEUS                                                    2717 1451   23
       SPIN          0.0                                          2717 1451   24
       PARITY        1.0                                          2717 1451   25
NATURAL ABUNDANCE   26.50 16     %                                2717 1451   26
                                1        451         28          02717 1451   27
                                8        457          5          02717 1451   28
 0.000000+0 0.000000+0          0          0          0          02717 1  099999
                                                                  2717 0  0    0
 7.41820+04 1.80385+02          0          0          1          02717 8457    1
 0.00000+00 0.00000+00          0          0          6          02717 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002717 8457    3
 0.00000+00 1.00000+00          0          0          6          02717 8457    4
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+00 0.00000+002717 8457    5
                                                                  2717 8  099999
                                                                  2717 0  0    0
                                                                     0 0  0    0
 7.418300+4 1.813790+2         -1          0          2          12718 1451    1
 0.000000+0 1.000000+0          0          0          0          62718 1451    2
 0.000000+0 0.000000+0          0          0          4        3112718 1451    3
 0.000000+0 0.000000+0          0          0         22          22718 1451    4
 74-W -183 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2718 1451    5
                      DIST-NOV07                       261107     2718 1451    6
----JEFF-311          MATERIAL 2718                               2718 1451    7
-----RADIOACTIVE DECAY DATA                                       2718 1451    8
------ENDF-6 FORMAT                                               2718 1451    9
******************************************************************2718 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2718 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2718 1451   12
**             Original data taken from:  NUBASE                **2718 1451   13
******************************************************************2718 1451   14
******************************************************************2718 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2718 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2718 1451   17
                                                                  2718 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2718 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2718 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2718 1451   21
******************************************************************2718 1451   22
LONG-LIVED NUCLEUS                                                2718 1451   23
       SPIN          0.5                                          2718 1451   24
       PARITY       -1.0                                          2718 1451   25
NATURAL ABUNDANCE   14.31 4      %                                2718 1451   26
                                1        451         28          02718 1451   27
                                8        457          7          02718 1451   28
 0.000000+0 0.000000+0          0          0          0          02718 1  099999
                                                                  2718 0  0    0
 7.41830+04 1.81379+02          0          0          0          02718 8457    1
 3.47134+24 0.00000+00          0          0          6          02718 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 1.18687+06 0.00000+002718 8457    3
 5.00000-01-1.00000+00          0          0         18          32718 8457    4
 4.00000+00 0.00000+00 1.68000+06 0.00000+00 3.34000-01 0.00000+002718 8457    5
 4.00000+00 1.00000+00 1.30496+06 0.00000+00 3.33000-01 0.00000+002718 8457    6
 4.00000+00 2.00000+00 5.74160+05 0.00000+00 3.33000-01 0.00000+002718 8457    7
                                                                  2718 8  099999
                                                                  2718 0  0    0
                                                                     0 0  0    0
 7.418300+4 1.813790+2         -1          0          2          12719 1451    1
 3.095000+5 1.000000+0          7          1          0          62719 1451    2
 0.000000+0 0.000000+0          0          0          4        3112719 1451    3
 0.000000+0 0.000000+0          0          0         52          22719 1451    4
 74-W -183MHAR+WIN    EVAL-JUN94 A.L. NICHOLS                     2719 1451    5
                      DIST-NOV07                       261107     2719 1451    6
----JEFF-311          MATERIAL 2719                               2719 1451    7
-----RADIOACTIVE DECAY DATA                                       2719 1451    8
------ENDF-6 FORMAT                                               2719 1451    9
******************************************************************2719 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2719 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2719 1451   12
**             Original data taken from:  UKPADD67              **2719 1451   13
******************************************************************2719 1451   14
          R B FIRESTONE         NUCL DATA SHEETS 52 (1987) 715    2719 1451   15
          R B FIRESTONE         NUCL DATA SHEETS 65 (1992) 589    2719 1451   16
          C J GALLAGHER, H L NIELSEN  NUCL PHYS 24 (1961) 422:    2719 1451   17
                                                       HALF-LIFE  2719 1451   18
          W D SCHMIDT-OTT ET AL       Z PHYS 162 (1961) 329:      2719 1451   19
                                                       HALF-LIFE  2719 1451   20
          T KAMINISHI, C KOJIMA       JAPANESE J APPL PHYS        2719 1451   21
                                          2 (1963) 399:HALF-LIFE  2719 1451   22
          E J BUTTON, T M SMITH      US NAVAL POSTGRADUATE SCHOOL 2719 1451   23
                                     MSC THESIS, AD-620384 (1965):2719 1451   24
                                                       HALF-LIFE  2719 1451   25
          W T K JOHNSON, C E DICK    NUCL INSTRUMS METHS          2719 1451   26
                                         99 (1972) 221:HALF-LIFE  2719 1451   27
          J J MURRAY ET AL      PHYS REV 97 (1955) 1007           2719 1451   28
          W F EDWARDS ET AL     NUCL PHYS 63 (1965) 97            2719 1451   29
          U GRUBER ET AL        Z NATURFORSCH 20A (1965) 929      2719 1451   30
                                                                  2719 1451   31
THE DECAY SCHEME OF W-183M (HALF-LIFE OF 5.25 SEC) WAS BASED ON   2719 1451   32
THE GAMMA-RAY CASCADE FROM THE 309.5 KEV METASTABLE STATE, THE    2719 1451   33
LOWER-ENERGY NUCLEAR LEVELS OF W-183, AND THEIR DEPOPULATION.     2719 1451   34
GAMMA-RAY DATA FROM THE STUDIES OF MURRAY ET AL, EDWARDS ET AL    2719 1451   35
AND GRUBER ET AL WERE USED IN CONJUNCTION WITH THE THEORETICAL    2719 1451   36
INTERNAL CONVERSION COEFFICIENTS AND TRANSITION PROBABILITIES TO  2719 1451   37
DERIVE THE ABSOLUTE EMISSION PROBABILITIES OF THE GAMMA-RAY       2719 1451   38
TRANSITIONS (ASSUMING 99.4%M1 + 0.6%E2 FOR 46.485 KEV, 98.6%M1 +  2719 1451   39
1.4%E2 FOR 52.596 KEV AND 76%M1 + 24%E2 FOR 107.933 KEV GAMMA-RAY 2719 1451   40
TRANSITIONS).  STUDIES ARE REQUIRED TO CONFIRM THESE DATA.        2719 1451   41
ALL OF THE GAMMA-RAY EMISSIONS OF W-183M CAN BE IDENTIFIED        2719 1451   42
DIRECTLY WITH THE BETA DECAY OF PARENT TA-183, ALTHOUGH TWO       2719 1451   43
SEPARATE DATA FILES HAVE BEEN ESTABLISHED.                        2719 1451   44
                                                                  2719 1451   45
                                                                  2719 1451   46
      MEAN GAMMA ENERGY              =     45.5393  KEV           2719 1451   47
      MEAN X-RAY ENERGY              =     79.8488  KEV           2719 1451   48
      MEAN AUGER ELECTRON ENERGY     =     22.0811  KEV           2719 1451   49
      MEAN CONVERSION ELECTRON ENERGY=    161.9043  KEV           2719 1451   50
      EFFECTIVE Q VALUE              =    309.5000  KEV           2719 1451   51
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0010                2719 1451   52
      CALCULATED Q VALUE             =    309.3735  KEV           2719 1451   53
      % DEVIATION                    =      0.0409                2719 1451   54
                                                                  2719 1451   55
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2719 1451   56
                                1        451         58          12719 1451   57
                                8        457         79          12719 1451   58
 0.000000+0 0.000000+0          0          0          0          02719 1  099999
                                                                  2719 0  0    0
7.41830E+041.81379E+02          7          1          0          32719 8457    1
5.25000E+007.00000E-02          0          0          6          02719 8457    2
1.83985E+051.63403E+041.25388E+058.16030E+030.00000E+000.00000E+002719 8457    3
5.50000E+00 1.0000E+00          0          0          6          12719 8457    4
3.00000E+000.00000E+003.09500E+053.00000E+001.00000E+000.00000E+002719 8457    5
0.00000E+000.00000E+00          0          0          6          62719 8457    6
1.89000E-010.00000E+004.55393E+041.68290E+030.00000E+000.00000E+002719 8457    7
4.64852E+042.00000E-01          0          0         12          02719 8457    8
3.00000E+000.00000E+003.22751E-011.58730E-020.00000E+000.00000E+002719 8457    9
8.60000E+004.98800E-010.00000E+000.00000E+006.70000E+003.88600E-012719 8457   10
5.25966E+043.00000E-01          0          0         12          02719 8457   11
3.00000E+000.00000E+003.59788E-012.11640E-020.00000E+000.00000E+002719 8457   12
6.36000E+004.00680E-010.00000E+000.00000E+004.89000E+003.08070E-012719 8457   13
9.90818E+049.00000E-02          0          0         12          02719 8457   14
3.00000E+000.00000E+004.33862E-011.58730E-020.00000E+000.00000E+002719 8457   15
4.10000E+002.00900E-018.80000E-014.31200E-022.30000E+001.12700E-012719 8457   16
1.02485E+053.00000E+00          0          0         12          02719 8457   17
3.00000E+000.00000E+001.28042E-011.58730E-030.00000E+000.00000E+002719 8457   18
4.03000E+014.83600E-012.77000E+013.32400E-019.10000E+001.09200E-012719 8457   19
1.07934E+052.00000E-01          0          0         12          02719 8457   20
3.00000E+000.00000E+001.00000E+007.93651E-020.00000E+000.00000E+002719 8457   21
3.85000E+004.00400E-012.70000E+002.80800E-017.70000E-018.00800E-022719 8457   22
1.60530E+053.00000E-01          0          0         12          02719 8457   23
3.00000E+000.00000E+002.67725E-017.93651E-030.00000E+000.00000E+002719 8457   24
6.80000E-015.03200E-023.00000E-012.22000E-022.75000E-012.03500E-022719 8457   25
0.00000E+008.00000E+00          0          0          6         192719 8457   26
1.00000E+000.00000E+001.83985E+051.83985E+040.00000E+000.00000E+002719 8457   27
2.27100E+031.13550E+02          0          0          6          02719 8457   28
3.00000E+000.00000E+003.76959E+003.76959E-010.00000E+000.00000E+002719 8457   29
6.52600E+033.26300E+02          0          0          6          02719 8457   30
3.00000E+000.00000E+001.64446E+001.64446E-010.00000E+000.00000E+002719 8457   31
2.95568E+041.47784E+03          0          0          6          02719 8457   32
3.00000E+000.00000E+007.21600E-027.21600E-030.00000E+000.00000E+002719 8457   33
3.29600E+041.64800E+03          0          0          6          02719 8457   34
3.00000E+000.00000E+006.70340E-016.70340E-020.00000E+000.00000E+002719 8457   35
3.62784E+041.81392E+03          0          0          6          02719 8457   36
3.00000E+000.00000E+004.08700E-014.08700E-020.00000E+000.00000E+002719 8457   37
3.84086E+041.92043E+03          0          0          6          02719 8457   38
3.00000E+000.00000E+005.10300E-015.10300E-020.00000E+000.00000E+002719 8457   39
4.23898E+042.11949E+03          0          0          6          02719 8457   40
3.00000E+000.00000E+003.32520E-013.32520E-020.00000E+000.00000E+002719 8457   41
4.42142E+042.21071E+03          0          0          6          02719 8457   42
3.00000E+000.00000E+001.15900E-011.15900E-020.00000E+000.00000E+002719 8457   43
5.03256E+042.51628E+03          0          0          6          02719 8457   44
3.00000E+000.00000E+009.99600E-029.99600E-030.00000E+000.00000E+002719 8457   45
5.11450E+042.55725E+03          0          0          6          02719 8457   46
3.00000E+000.00000E+005.45231E-025.45231E-030.00000E+000.00000E+002719 8457   47
8.88750E+044.44375E+03          0          0          6          02719 8457   48
3.00000E+000.00000E+001.88600E-011.88600E-020.00000E+000.00000E+002719 8457   49
9.10051E+044.55026E+03          0          0          6          02719 8457   50
3.00000E+000.00000E+001.51800E-021.51800E-030.00000E+000.00000E+002719 8457   51
9.22782E+044.61391E+03          0          0          6          02719 8457   52
3.00000E+000.00000E+002.20220E-012.20220E-020.00000E+000.00000E+002719 8457   53
9.68108E+044.84054E+03          0          0          6          02719 8457   54
3.00000E+000.00000E+007.54400E-027.54400E-030.00000E+000.00000E+002719 8457   55
9.77268E+044.88634E+03          0          0          6          02719 8457   56
3.00000E+000.00000E+001.45530E-011.45530E-020.00000E+000.00000E+002719 8457   57
1.00214E+055.01070E+03          0          0          6          02719 8457   58
3.00000E+000.00000E+008.47000E-028.47000E-030.00000E+000.00000E+002719 8457   59
1.05663E+055.28313E+03          0          0          6          02719 8457   60
3.00000E+000.00000E+007.18200E-027.18200E-030.00000E+000.00000E+002719 8457   61
1.50323E+057.51617E+03          0          0          6          02719 8457   62
3.00000E+000.00000E+001.39150E-021.39150E-030.00000E+000.00000E+002719 8457   63
1.58259E+057.91296E+03          0          0          6          02719 8457   64
3.00000E+000.00000E+005.31300E-035.31300E-040.00000E+000.00000E+002719 8457   65
0.00000E+009.00000E+00          0          0          6          62719 8457   66
1.00000E+000.00000E+007.98488E+047.98488E+030.00000E+000.00000E+002719 8457   67
2.27100E+034.54200E+01          0          0          6          02719 8457   68
3.00000E+000.00000E+006.67524E-026.67524E-030.00000E+000.00000E+002719 8457   69
8.59500E+031.71900E+02          0          0          6          02719 8457   70
3.00000E+000.00000E+007.04769E-017.04769E-020.00000E+000.00000E+002719 8457   71
5.79817E+041.15963E+03          0          0          6          02719 8457   72
3.00000E+000.00000E+003.49476E-013.49476E-020.00000E+000.00000E+002719 8457   73
5.93182E+041.18636E+03          0          0          6          02719 8457   74
3.00000E+000.00000E+006.06728E-016.06728E-020.00000E+000.00000E+002719 8457   75
6.72000E+041.34400E+03          0          0          6          02719 8457   76
3.00000E+000.00000E+002.05074E-012.05074E-020.00000E+000.00000E+002719 8457   77
6.91000E+041.38200E+03          0          0          6          02719 8457   78
3.00000E+000.00000E+005.21787E-025.21787E-030.00000E+000.00000E+002719 8457   79
                                                                  2719 8  099999
                                                                  2719 0  0    0
                                                                     0 0  0    0
 7.418400+4 1.823710+2         -1          0          2          12720 1451    1
 0.000000+0 1.000000+0          0          0          0          62720 1451    2
 0.000000+0 0.000000+0          0          0          4        3112720 1451    3
 0.000000+0 0.000000+0          0          0         22          22720 1451    4
 74-W -184 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2720 1451    5
                      DIST-NOV07                       261107     2720 1451    6
----JEFF-311          MATERIAL 2720                               2720 1451    7
-----RADIOACTIVE DECAY DATA                                       2720 1451    8
------ENDF-6 FORMAT                                               2720 1451    9
******************************************************************2720 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2720 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2720 1451   12
**             Original data taken from:  NUBASE                **2720 1451   13
******************************************************************2720 1451   14
******************************************************************2720 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2720 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2720 1451   17
                                                                  2720 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2720 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2720 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2720 1451   21
******************************************************************2720 1451   22
LONG-LIVED NUCLEUS                                                2720 1451   23
       SPIN          0.0                                          2720 1451   24
       PARITY        1.0                                          2720 1451   25
NATURAL ABUNDANCE   30.64 2      %                                2720 1451   26
                                1        451         28          02720 1451   27
                                8        457          5          02720 1451   28
 0.000000+0 0.000000+0          0          0          0          02720 1  099999
                                                                  2720 0  0    0
 7.41840+04 1.82371+02          0          0          0          02720 8457    1
 1.26230+25 0.00000+00          0          0          6          02720 8457    2
 0.00000+00 0.00000+00 0.00000+00 0.00000+00 1.65620+06 0.00000+002720 8457    3
 0.00000+00 1.00000+00          0          0          6          12720 8457    4
 4.00000+00 0.00000+00 1.65620+06 0.00000+00 1.00000+00 0.00000+002720 8457    5
                                                                  2720 8  099999
                                                                  2720 0  0    0
                                                                     0 0  0    0
 7.418500+4 1.833650+2         -1          0          2          12721 1451    1
 0.000000+0 1.000000+0          0          0          0          62721 1451    2
 0.000000+0 0.000000+0          0          0          4        3112721 1451    3
 0.000000+0 0.000000+0          0          0         42          22721 1451    4
 74-W -185 HAR+WIN    EVAL-JAN91 A.L. NICHOLS                     2721 1451    5
                      DIST-NOV07                       261107     2721 1451    6
----JEFF-311          MATERIAL 2721                               2721 1451    7
-----RADIOACTIVE DECAY DATA                                       2721 1451    8
------ENDF-6 FORMAT                                               2721 1451    9
******************************************************************2721 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2721 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2721 1451   12
**             Original data taken from:  UKPADD67              **2721 1451   13
******************************************************************2721 1451   14
      E.BROWNE                     NUCL DATA SHEETS 58(1989)441   2721 1451   15
      C.R.PIERCE, D.F.SHOOK   NUCL SCI ENG 31(1968)431:HALF-LIFE  2721 1451   16
      J.F.EMERY ET AL         NUCL SCI ENG 48(1972)319:HALF-LIFE  2721 1451   17
      R.P.SHARMA ET AL        NUCL PHYS   A152(1970)225           2721 1451   18
      R.PRASAD BABU ET AL     PHYS REV    13C(1976)1267           2721 1451   19
      D.S.BRENNER ET AL       PHYS REV    16C(1977)747            2721 1451   20
                                                                  2721 1451   21
          THE HALF-LIFE MEASUREMENT OF EMERY ET AL HAS BEEN       2721 1451   22
      ADOPTED.  BETA DECAY STUDIES OF SHARMA WERE USED TO DERIVE  2721 1451   23
      THE BETA-PARTICLE EMISSION PROBABILITIES, AND THESE DATA    2721 1451   24
      WERE ADOPTED (IN CONJUNCTION WITH EQUIVALENT OS-185         2721 1451   25
      MEASUREMENTS OF BRENNER ET AL AND THEORETICAL INTERNAL      2721 1451   26
      CONVERSION COEFFICIENTS) TO CALCULATE THE EMISSION          2721 1451   27
      PROBABILITY OF THE 125.36 KEV GAMMA-RAY (M1 TRANSITION).    2721 1451   28
                                                                  2721 1451   29
                                                                  2721 1451   30
      MEAN BETA- ENERGIES:-                                       2721 1451   31
   END POINT(MEV)= 0.3074  SHAPE= 2  MEAN= 0.0960  INT= 0.0007    2721 1451   32
   END POINT(MEV)= 0.4328  SHAPE= 1  MEAN= 0.1268  INT= 0.9993    2721 1451   33
                                                                  2721 1451   34
      MEAN GAMMA ENERGY              =      0.0233  KEV           2721 1451   35
      MEAN BETA- ENERGY              =    126.7656  KEV           2721 1451   36
      BETA- + NEUTRINO ENERGY        =    432.7122  KEV           2721 1451   37
      MEAN X-RAY ENERGY              =      0.0268  KEV           2721 1451   38
      MEAN AUGER ELECTRON ENERGY     =      0.0044  KEV           2721 1451   39
      MEAN CONVERSION ELECTRON ENERGY=      0.0329  KEV           2721 1451   40
      EFFECTIVE Q VALUE              =    432.8000  KEV           2721 1451   41
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.2079                2721 1451   42
      CALCULATED Q VALUE             =    432.7997  KEV           2721 1451   43
      % DEVIATION                    =      0.0001                2721 1451   44
                                                                  2721 1451   45
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2721 1451   46
                                1        451         48          12721 1451   47
                                8        457         44          12721 1451   48
 0.000000+0 0.000000+0          0          0          0          02721 1  099999
                                                                  2721 0  0    0
7.41850E+041.83365E+02          0          0          0          42721 8457    1
6.48864E+062.59200E+04          0          0          6          02721 8457    2
1.26803E+052.64395E+025.01596E+015.68766E+000.00000E+000.00000E+002721 8457    3
1.50000E+00-1.0000E+00          0          0          6          12721 8457    4
1.00000E+000.00000E+004.32800E+059.00000E+021.00000E+000.00000E+002721 8457    5
0.00000E+000.00000E+00          0          0          6          12721 8457    6
1.86000E-044.00000E-052.33170E+015.01440E+000.00000E+000.00000E+002721 8457    7
1.25360E+051.00000E+01          0          0         12          02721 8457    8
1.00000E+000.00000E+001.00000E+000.00000E+000.00000E+000.00000E+002721 8457    9
2.76000E+006.07200E-022.30000E+005.06000E-023.60000E-017.92000E-032721 8457   10
0.00000E+001.00000E+00          0          0          6          22721 8457   11
1.00000E+000.00000E+001.26766E+052.64374E+020.00000E+000.00000E+002721 8457   12
3.07400E+059.00000E+02          0          0          6          02721 8457   13
1.00000E+002.00000E+007.00000E-041.40000E-040.00000E+000.00000E+002721 8457   14
4.32800E+059.00000E+02          0          0          6          02721 8457   15
1.00000E+001.00000E+009.99300E-011.40000E-040.00000E+000.00000E+002721 8457   16
0.00000E+008.00000E+00          0          0          6          62721 8457   17
1.00000E+000.00000E+003.72974E+013.72974E+000.00000E+000.00000E+002721 8457   18
2.36200E+031.18100E+02          0          0          6          02721 8457   19
1.00000E+000.00000E+006.41107E-046.41107E-050.00000E+000.00000E+002721 8457   20
6.70300E+033.35150E+02          0          0          6          02721 8457   21
1.00000E+000.00000E+002.85994E-042.85994E-050.00000E+000.00000E+002721 8457   22
5.26720E+042.63360E+03          0          0          6          02721 8457   23
1.00000E+000.00000E+001.75398E-051.75398E-060.00000E+000.00000E+002721 8457   24
5.36836E+042.68418E+03          0          0          6          02721 8457   25
1.00000E+000.00000E+004.27800E-044.27800E-050.00000E+000.00000E+002721 8457   26
1.14825E+055.74124E+03          0          0          6          02721 8457   27
1.00000E+000.00000E+006.69600E-056.69600E-060.00000E+000.00000E+002721 8457   28
1.22998E+056.14990E+03          0          0          6          02721 8457   29
1.00000E+000.00000E+001.86000E-051.86000E-060.00000E+000.00000E+002721 8457   30
0.00000E+009.00000E+00          0          0          6          62721 8457   31
1.00000E+000.00000E+002.68426E+012.68426E+000.00000E+000.00000E+002721 8457   32
2.36200E+034.72400E+01          0          0          6          02721 8457   33
1.00000E+000.00000E+001.17514E-051.17514E-060.00000E+000.00000E+002721 8457   34
8.86400E+031.77280E+02          0          0          6          02721 8457   35
1.00000E+000.00000E+001.30907E-041.30907E-050.00000E+000.00000E+002721 8457   36
5.97179E+041.19436E+03          0          0          6          02721 8457   37
1.00000E+000.00000E+001.18270E-041.18270E-050.00000E+000.00000E+002721 8457   38
6.11400E+041.22280E+03          0          0          6          02721 8457   39
1.00000E+000.00000E+002.04619E-042.04619E-050.00000E+000.00000E+002721 8457   40
6.92000E+041.38400E+03          0          0          6          02721 8457   41
1.00000E+000.00000E+006.97749E-056.97749E-060.00000E+000.00000E+002721 8457   42
7.12000E+041.42400E+03          0          0          6          02721 8457   43
1.00000E+000.00000E+001.75972E-051.75972E-060.00000E+000.00000E+002721 8457   44
                                                                  2721 8  099999
                                                                  2721 0  0    0
                                                                     0 0  0    0
 7.418500+4 1.833650+2         -1          0          2          12722 1451    1
 1.974300+5 1.000000+0          6          1          0          62722 1451    2
 0.000000+0 0.000000+0          0          0          4        3112722 1451    3
 0.000000+0 0.000000+0          0          0         41          22722 1451    4
 74-W -185MHAR+WIN    EVAL-JAN91 A.L. NICHOLS                     2722 1451    5
                      DIST-NOV07                       261107     2722 1451    6
----JEFF-311          MATERIAL 2722                               2722 1451    7
-----RADIOACTIVE DECAY DATA                                       2722 1451    8
------ENDF-6 FORMAT                                               2722 1451    9
******************************************************************2722 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2722 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2722 1451   12
**             Original data taken from:  UKPADD67              **2722 1451   13
******************************************************************2722 1451   14
      E.BROWNE                     NUCL DATA SHEETS 58(1989)441   2722 1451   15
      P.J.DALY ET AL               NUCL PHYS      A123(1969)186   2722 1451   16
      T.KUROYANAGI, T.TAMURA       NUCL PHYS      A133(1969)554   2722 1451   17
      S.C.GUJRATHI, J.M.D'AURIA    CAN J PHYS       48(1970)502   2722 1451   18
      B.P.PATHAK ET AL             INDIAN J PHYS    44(1970)19    2722 1451   19
      S.V.MALMSKOG ET AL           ARKIV FYSIK      40(1970)247   2722 1451   20
                                                                  2722 1451   21
          A COMPLEX DECAY SCHEME WAS DERIVED DESPITE A NUMBER OF  2722 1451   22
      MINOR DISCREPANCIES BETWEEN THE MEASURED GAMMA-RAY EMISSION 2722 1451   23
      PROBABILITIES.  WEIGHTED MEAN DATA WERE OBTAINED FOR THE    2722 1451   24
      RELATIVE GAMMA-RAY EMISSION PROBABILITIES FROM THE STUDIES  2722 1451   25
      OF DALY ET AL, KUROYANAGI ET AL, GUJRATHI ET AL, PATHAK ET  2722 1451   26
      AL AND MALMSKOG ET AL, WITH THE OCCASIONAL REJECTION OF A   2722 1451   27
      SPECIFIC OUTLIER VALUE.  ESTIMATES WERE MADE OF THE GAMMA-  2722 1451   28
      RAY TRANSITION PROBABILITIES FOR 9.5, 23.7 AND 69.8 KEV     2722 1451   29
      TRANSITIONS BASED ON THE POPULATION/DEPOPULATION OF THE     2722 1451   30
      ASSOCIATED NUCLEAR LEVELS.  A COMPREHENSIVE DECAY SCHEME    2722 1451   31
      WAS CONSTRUCTED ON THIS BASIS TO DETERMINE THE              2722 1451   32
      NORMALISATION FACTOR FOR THE GAMMA-RAY EMISSIONS.           2722 1451   33
                                                                  2722 1451   34
                                                                  2722 1451   35
      MEAN GAMMA ENERGY              =     17.4133  KEV           2722 1451   36
      MEAN X-RAY ENERGY              =      8.3255  KEV           2722 1451   37
      MEAN AUGER ELECTRON ENERGY     =     11.8211  KEV           2722 1451   38
      MEAN CONVERSION ELECTRON ENERGY=    160.1689  KEV           2722 1451   39
      EFFECTIVE Q VALUE              =    197.4300  KEV           2722 1451   40
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.0253                2722 1451   41
      CALCULATED Q VALUE             =    197.7289  KEV           2722 1451   42
      % DEVIATION                    =     -0.1514                2722 1451   43
                                                                  2722 1451   44
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2722 1451   45
                                1        451         47          12722 1451   46
                                8        457        141          12722 1451   47
 0.000000+0 0.000000+0          0          0          0          02722 1  099999
                                                                  2722 0  0    0
7.41850E+041.83365E+02          6          1          0          32722 8457    1
1.00000E+022.00000E+00          0          0          6          02722 8457    2
1.71990E+051.60605E+042.57389E+041.57517E+030.00000E+000.00000E+002722 8457    3
5.50000E+00 1.0000E+00          0          0          6          12722 8457    4
3.00000E+000.00000E+001.97430E+055.00000E+011.00000E+000.00000E+002722 8457    5
0.00000E+000.00000E+00          0          0          6         142722 8457    6
5.40000E-024.00000E-031.74133E+041.33717E+030.00000E+000.00000E+002722 8457    7
9.50000E+031.00000E+02          0          0         12          02722 8457    8
3.00000E+000.00000E+001.37000E-081.10000E-090.00000E+000.00000E+002722 8457    9
4.15000E+074.98000E+050.00000E+000.00000E+000.00000E+000.00000E+002722 8457   10
2.35600E+044.00000E+01          0          0         12          02722 8457   11
3.00000E+000.00000E+002.30000E-028.00000E-030.00000E+000.00000E+002722 8457   12
1.10000E+021.00100E+010.00000E+000.00000E+007.60000E+016.91600E+002722 8457   13
2.37000E+041.00000E+02          0          0         12          02722 8457   14
3.00000E+000.00000E+001.40000E-041.00000E-050.00000E+000.00000E+002722 8457   15
8.20000E+031.96800E+020.00000E+000.00000E+006.00000E+031.44000E+022722 8457   16
4.23000E+041.00000E+02          0          0         12          02722 8457   17
3.00000E+000.00000E+001.20000E-023.00000E-030.00000E+000.00000E+002722 8457   18
1.90000E+021.00700E+010.00000E+000.00000E+001.40000E+027.42000E+002722 8457   19
6.58800E+044.00000E+01          0          0         12          02722 8457   20
3.00000E+000.00000E+001.00000E+000.00000E+000.00000E+000.00000E+002722 8457   21
1.40000E+019.94000E-010.00000E+000.00000E+001.04000E+017.38400E-012722 8457   22
6.98000E+041.00000E+02          0          0         12          02722 8457   23
3.00000E+000.00000E+004.50000E-031.00000E-030.00000E+000.00000E+002722 8457   24
1.80000E+011.00800E+000.00000E+000.00000E+001.25000E+017.00000E-012722 8457   25
9.33100E+046.00000E+01          0          0         12          02722 8457   26
3.00000E+000.00000E+005.00000E-032.00000E-030.00000E+000.00000E+002722 8457   27
5.50000E+009.90000E-021.00000E+001.80000E-023.20000E+005.76000E-022722 8457   28
9.46000E+041.00000E+02          0          0         12          02722 8457   29
3.00000E+000.00000E+001.80000E-022.00000E-030.00000E+000.00000E+002722 8457   30
5.40000E+001.02600E-012.80000E+005.32000E-021.90000E+003.61000E-022722 8457   31
1.07860E+059.00000E+01          0          0         12          02722 8457   32
3.00000E+000.00000E+007.40000E-025.00000E-030.00000E+000.00000E+002722 8457   33
3.30000E+009.90000E-021.40000E+004.20000E-021.30000E+003.90000E-022722 8457   34
1.22020E+057.00000E+01          0          0         12          02722 8457   35
3.00000E+000.00000E+001.70000E-021.00000E-030.00000E+000.00000E+002722 8457   36
2.30000E+009.89000E-021.40000E+006.02000E-026.30000E-012.70900E-022722 8457   37
1.31550E+059.00000E+01          0          0         12          02722 8457   38
3.00000E+000.00000E+008.00000E-014.00000E-020.00000E+000.00000E+002722 8457   39
2.00000E+015.00000E-011.40000E+003.50000E-021.05000E+012.62500E-012722 8457   40
1.64340E+057.00000E+01          0          0         12          02722 8457   41
3.00000E+000.00000E+001.05000E-015.00000E-030.00000E+000.00000E+002722 8457   42
6.20000E-019.92000E-032.85000E-014.56000E-032.50000E-014.00000E-032722 8457   43
1.73740E+055.00000E+01          0          0         12          02722 8457   44
3.00000E+000.00000E+005.40000E-012.00000E-020.00000E+000.00000E+002722 8457   45
5.20000E-019.88000E-032.45000E-014.65500E-031.95000E-013.70500E-032722 8457   46
1.87900E+053.00000E+01          0          0         12          02722 8457   47
3.00000E+000.00000E+001.42000E-017.00000E-030.00000E+000.00000E+002722 8457   48
6.00000E-011.02000E-024.40000E-017.48000E-031.20000E-012.04000E-032722 8457   49
0.00000E+008.00000E+00          0          0          6         382722 8457   50
1.00000E+000.00000E+001.71990E+051.71990E+040.00000E+000.00000E+002722 8457   51
2.27100E+031.13550E+02          0          0          6          02722 8457   52
3.00000E+000.00000E+002.44426E+002.44426E-010.00000E+000.00000E+002722 8457   53
6.52600E+033.26300E+02          0          0          6          02722 8457   54
3.00000E+000.00000E+009.32999E-019.32999E-020.00000E+000.00000E+002722 8457   55
7.22900E+033.61450E+02          0          0          6          02722 8457   56
3.00000E+000.00000E+003.07017E-023.07017E-030.00000E+000.00000E+002722 8457   57
1.33532E+046.67660E+02          0          0          6          02722 8457   58
3.00000E+000.00000E+009.43920E-029.43920E-030.00000E+000.00000E+002722 8457   59
1.34932E+046.74660E+02          0          0          6          02722 8457   60
3.00000E+000.00000E+004.53600E-024.53600E-030.00000E+000.00000E+002722 8457   61
2.12890E+041.06445E+03          0          0          6          02722 8457   62
3.00000E+000.00000E+004.22280E-024.22280E-030.00000E+000.00000E+002722 8457   63
2.14290E+041.07145E+03          0          0          6          02722 8457   64
3.00000E+000.00000E+001.66320E-021.66320E-030.00000E+000.00000E+002722 8457   65
2.37850E+041.18925E+03          0          0          6          02722 8457   66
3.00000E+000.00000E+002.70000E-042.70000E-050.00000E+000.00000E+002722 8457   67
2.50750E+041.25375E+03          0          0          6          02722 8457   68
3.00000E+000.00000E+002.72160E-032.72160E-040.00000E+000.00000E+002722 8457   69
3.20932E+041.60466E+03          0          0          6          02722 8457   70
3.00000E+000.00000E+009.07200E-029.07200E-030.00000E+000.00000E+002722 8457   71
3.83350E+041.91675E+03          0          0          6          02722 8457   72
3.00000E+000.00000E+005.59440E-035.59440E-040.00000E+000.00000E+002722 8457   73
4.00290E+042.00145E+03          0          0          6          02722 8457   74
3.00000E+000.00000E+003.24000E-023.24000E-030.00000E+000.00000E+002722 8457   75
5.11450E+042.55725E+03          0          0          6          02722 8457   76
3.00000E+000.00000E+003.54686E-033.54686E-040.00000E+000.00000E+002722 8457   77
5.24950E+042.62475E+03          0          0          6          02722 8457   78
3.00000E+000.00000E+001.28520E-031.28520E-040.00000E+000.00000E+002722 8457   79
5.56732E+042.78366E+03          0          0          6          02722 8457   80
3.00000E+000.00000E+005.61600E-015.61600E-020.00000E+000.00000E+002722 8457   81
5.95932E+042.97966E+03          0          0          6          02722 8457   82
3.00000E+000.00000E+003.03750E-033.03750E-040.00000E+000.00000E+002722 8457   83
6.20250E+043.10125E+03          0          0          6          02722 8457   84
3.00000E+000.00000E+006.04800E-026.04800E-030.00000E+000.00000E+002722 8457   85
6.36090E+043.18045E+03          0          0          6          02722 8457   86
3.00000E+000.00000E+001.94400E-011.94400E-020.00000E+000.00000E+002722 8457   87
6.75290E+043.37645E+03          0          0          6          02722 8457   88
3.00000E+000.00000E+001.33650E-031.33650E-040.00000E+000.00000E+002722 8457   89
8.31032E+044.15516E+03          0          0          6          02722 8457   90
3.00000E+000.00000E+008.64000E-048.64000E-050.00000E+000.00000E+002722 8457   91
8.43932E+044.21966E+03          0          0          6          02722 8457   92
3.00000E+000.00000E+001.84680E-031.84680E-040.00000E+000.00000E+002722 8457   93
9.10390E+044.55195E+03          0          0          6          02722 8457   94
3.00000E+000.00000E+003.51000E-043.51000E-050.00000E+000.00000E+002722 8457   95
9.23290E+044.61645E+03          0          0          6          02722 8457   96
3.00000E+000.00000E+006.80400E-046.80400E-050.00000E+000.00000E+002722 8457   97
9.48150E+044.74075E+03          0          0          6          02722 8457   98
3.00000E+000.00000E+001.61595E-031.61595E-040.00000E+000.00000E+002722 8457   99
9.76532E+044.88266E+03          0          0          6          02722 8457  100
3.00000E+000.00000E+005.19480E-035.19480E-040.00000E+000.00000E+002722 8457  101
1.04215E+055.21075E+03          0          0          6          02722 8457  102
3.00000E+000.00000E+007.14420E-037.14420E-040.00000E+000.00000E+002722 8457  103
1.05589E+055.27945E+03          0          0          6          02722 8457  104
3.00000E+000.00000E+002.39760E-032.39760E-040.00000E+000.00000E+002722 8457  105
1.11813E+055.59066E+03          0          0          6          02722 8457  106
3.00000E+000.00000E+005.78340E-045.78340E-050.00000E+000.00000E+002722 8457  107
1.18375E+055.91875E+03          0          0          6          02722 8457  108
3.00000E+000.00000E+003.37392E-033.37392E-040.00000E+000.00000E+002722 8457  109
1.19749E+055.98745E+03          0          0          6          02722 8457  110
3.00000E+000.00000E+002.47860E-042.47860E-050.00000E+000.00000E+002722 8457  111
1.21343E+056.06716E+03          0          0          6          02722 8457  112
3.00000E+000.00000E+004.53600E-014.53600E-020.00000E+000.00000E+002722 8457  113
1.29279E+056.46395E+03          0          0          6          02722 8457  114
3.00000E+000.00000E+003.49920E-013.49920E-020.00000E+000.00000E+002722 8457  115
1.54133E+057.70666E+03          0          0          6          02722 8457  116
3.00000E+000.00000E+001.41750E-031.41750E-040.00000E+000.00000E+002722 8457  117
1.62069E+058.10345E+03          0          0          6          02722 8457  118
3.00000E+000.00000E+004.81950E-044.81950E-050.00000E+000.00000E+002722 8457  119
1.63533E+058.17666E+03          0          0          6          02722 8457  120
3.00000E+000.00000E+005.68620E-035.68620E-040.00000E+000.00000E+002722 8457  121
1.71469E+058.57345E+03          0          0          6          02722 8457  122
3.00000E+000.00000E+002.33280E-032.33280E-040.00000E+000.00000E+002722 8457  123
1.77693E+058.88466E+03          0          0          6          02722 8457  124
3.00000E+000.00000E+009.20160E-049.20160E-050.00000E+000.00000E+002722 8457  125
1.85629E+059.28145E+03          0          0          6          02722 8457  126
3.00000E+000.00000E+003.06720E-043.06720E-050.00000E+000.00000E+002722 8457  127
0.00000E+009.00000E+00          0          0          6          62722 8457  128
1.00000E+000.00000E+008.32551E+038.32551E+020.00000E+000.00000E+002722 8457  129
2.27100E+034.54200E+01          0          0          6          02722 8457  130
3.00000E+000.00000E+004.32833E-024.32833E-030.00000E+000.00000E+002722 8457  131
8.59500E+031.71900E+02          0          0          6          02722 8457  132
3.00000E+000.00000E+003.99857E-013.99857E-020.00000E+000.00000E+002722 8457  133
5.79817E+041.15963E+03          0          0          6          02722 8457  134
3.00000E+000.00000E+002.27343E-022.27343E-030.00000E+000.00000E+002722 8457  135
5.93182E+041.18636E+03          0          0          6          02722 8457  136
3.00000E+000.00000E+003.94692E-023.94692E-030.00000E+000.00000E+002722 8457  137
6.72000E+041.34400E+03          0          0          6          02722 8457  138
3.00000E+000.00000E+001.33406E-021.33406E-030.00000E+000.00000E+002722 8457  139
6.91000E+041.38200E+03          0          0          6          02722 8457  140
3.00000E+000.00000E+003.39435E-033.39435E-040.00000E+000.00000E+002722 8457  141
                                                                  2722 8  099999
                                                                  2722 0  0    0
                                                                     0 0  0    0
 7.418600+4 1.843570+2         -1          0          2          12723 1451    1
 0.000000+0 1.000000+0          0          0          0          62723 1451    2
 0.000000+0 0.000000+0          0          0          4        3112723 1451    3
 0.000000+0 0.000000+0          0          0         22          22723 1451    4
 74-W -186 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2723 1451    5
                      DIST-NOV07                       261107     2723 1451    6
----JEFF-311          MATERIAL 2723                               2723 1451    7
-----RADIOACTIVE DECAY DATA                                       2723 1451    8
------ENDF-6 FORMAT                                               2723 1451    9
******************************************************************2723 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2723 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2723 1451   12
**             Original data taken from:  NUBASE                **2723 1451   13
******************************************************************2723 1451   14
******************************************************************2723 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2723 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2723 1451   17
                                                                  2723 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2723 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2723 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2723 1451   21
******************************************************************2723 1451   22
LONG-LIVED NUCLEUS                                                2723 1451   23
       SPIN          0.0                                          2723 1451   24
       PARITY        1.0                                          2723 1451   25
NATURAL ABUNDANCE   28.43 19     %                                2723 1451   26
                                1        451         28          02723 1451   27
                                8        457          6          02723 1451   28
 0.000000+0 0.000000+0          0          0          0          02723 1  099999
                                                                  2723 0  0    0
 7.41860+04 1.84357+02          0          0          0          02723 8457    1
 1.86190+25 0.00000+00          0          0          6          02723 8457    2
 2.44999+05 0.00000+00 0.00000+00 0.00000+00 5.62300+05 0.00000+002723 8457    3
 0.00000+00 1.00000+00          0          0         12          22723 8457    4
 1.10000+00 0.00000+00 4.89998+05 0.00000+00 5.00000-01 0.00000+002723 8457    5
 4.00000+00 0.00000+00 1.12460+06 0.00000+00 5.00000-01 0.00000+002723 8457    6
                                                                  2723 8  099999
                                                                  2723 0  0    0
                                                                     0 0  0    0
 7.418600+4 1.843570+2         -1          0          2          12724 1451    1
 3.542800+6 1.000000+0          1          1          0          62724 1451    2
 0.000000+0 0.000000+0          0          0          4        3112724 1451    3
 0.000000+0 0.000000+0          0          0         18          22724 1451    4
 74-W -186MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2724 1451    5
                      DIST-NOV07                       261107     2724 1451    6
----JEFF-311          MATERIAL 2724                               2724 1451    7
-----RADIOACTIVE DECAY DATA                                       2724 1451    8
------ENDF-6 FORMAT                                               2724 1451    9
******************************************************************2724 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2724 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2724 1451   12
**             Original data taken from:  NUBASE                **2724 1451   13
******************************************************************2724 1451   14
******************************************************************2724 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2724 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2724 1451   17
                                                                  2724 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2724 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2724 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2724 1451   21
******************************************************************2724 1451   22
                                1        451         24          02724 1451   23
                                8        457          5          02724 1451   24
 0.000000+0 0.000000+0          0          0          0          02724 1  099999
                                                                  2724 0  0    0
 7.41860+04 1.84357+02          1          1          0          02724 8457    1
 3.00000-03 0.00000+00          0          0          6          02724 8457    2
 0.00000+00 0.00000+00 3.54280+06 0.00000+00 0.00000+00 0.00000+002724 8457    3
 1.60000+01 1.00000+00          0          0          6          12724 8457    4
 3.00000+00 0.00000+00 3.54280+06 0.00000+00 1.00000+00 0.00000+002724 8457    5
                                                                  2724 8  099999
                                                                  2724 0  0    0
                                                                     0 0  0    0
 7.418700+4 1.853510+2         -1          0          2          12725 1451    1
 0.000000+0 1.000000+0          0          0          0          62725 1451    2
 0.000000+0 0.000000+0          0          0          4        3112725 1451    3
 0.000000+0 0.000000+0          0          0         72          22725 1451    4
 74-W -187 HAR+WIN    EVAL-OCT91 A.L. NICHOLS                     2725 1451    5
                      DIST-NOV07                       261107     2725 1451    6
----JEFF-311          MATERIAL 2725                               2725 1451    7
-----RADIOACTIVE DECAY DATA                                       2725 1451    8
------ENDF-6 FORMAT                                               2725 1451    9
******************************************************************2725 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2725 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2725 1451   12
**             Original data taken from:  UKPADD67              **2725 1451   13
******************************************************************2725 1451   14
      R.B.FIRESTONE                 NUCL DATA SHEETS 62(1991)159  2725 1451   15
      Y.A.ELLIS-AKOVALI             NUCL DATA SHEETS 36(1982)559  2725 1451   16
      G.G.EICHHOLZ            PHYS REV 89(1953)525:HALF-LIFE      2725 1451   17
      H.W.WRIGHT ET AL        NUCL SCI ENG 2(1957)427:HALF-LIFE   2725 1451   18
      R.L.ANDELIN        J INORG NUCL CHEM 26(1964)1117:HALF-LIFE 2725 1451   19
      J.M.CORK ET AL                PHYS REV 89(1953)1291         2725 1451   20
      A.W.HERMAN ET AL        CAN J PHYS 48(1970)1040             2725 1451   21
      S.M.DARWISH ET AL             NUCL PHYS A236(1974)340       2725 1451   22
      D.S.BRENNER, R.A.MEYER        PHYS REV 13C(1976)1288        2725 1451   23
      S.S.SOOCH ET AL         SYMP 25Y NUCL PHYS & SOLID STATE    2725 1451   24
                    PHYSICS, BOMBAY, DEPT ATOMIC ENERGY (1981)135 2725 1451   25
                                                                  2725 1451   26
          THE GAMMA-RAY MEASUREMENTS OF HERMAN ET AL, SOOCH ET AL,2725 1451   27
      AND BRENNER AND MEYER WERE USED TO CONSTRUCT A COMPLEX DECAY2725 1451   28
      SCHEME.  DATA REPORTED BY BRENNER AND MEYER WERE            2725 1451   29
      PARTICULARLY COMPREHENSIVE. A NUMBER OF ILL-DEFINED,        2725 1451   30
      LOW-INTENSITY TRANSITIONS WERE DISCARDED IN THIS EVALUATION.2725 1451   31
          A VALUE OF 0.30(2) WAS ADOPTED FOR THE BETA BRANCH TO   2725 1451   32
      THE GROUND STATE OF RE-187, RESULTING IN A NORMALISATION    2725 1451   33
      FACTOR OF 0.27(1) FOR THE GAMMA-RAY TRANSITIONS.  SOME      2725 1451   34
      INCONSISTENCIES OCCUR, PARTICULARLY IN THE POPULATION AND   2725 1451   35
      DEPOPULATION OF THE 206.25 KEV NUCLEAR LEVEL.  FIRESTONE HAS2725 1451   36
      PROPOSED ADDITIONAL NUCLEAR LEVELS TO ACCOMMODATE SOME OF   2725 1451   37
      THE GAMMA-RAY EMISSIONS OBSERVED BY BRENNER AND MEYER; THESE2725 1451   38
      UNCERTAIN LEVELS HAVE NOT BEEN INCLUDED IN THE CURRENT      2725 1451   39
      EVALUATION, AND FURTHER ASSESSMENT IS REQUIRED IN           2725 1451   40
      CONJUNCTION WITH GAMMA-RAY MEASUREMENTS TO ASSIST IN        2725 1451   41
      RESOLVING SUCH DIFFICULTIES AND MINOR INCONSISTENCIES.      2725 1451   42
                                                                  2725 1451   43
                                                                  2725 1451   44
      MEAN BETA- ENERGIES:-                                       2725 1451   45
   END POINT(MEV)= 0.0820  SHAPE= 1  MEAN= 0.0212  INT= 0.0000    2725 1451   46
   END POINT(MEV)= 0.0920  SHAPE= 1  MEAN= 0.0239  INT= 0.0000    2725 1451   47
   END POINT(MEV)= 0.1220  SHAPE= 1  MEAN= 0.0321  INT= 0.0001    2725 1451   48
   END POINT(MEV)= 0.3520  SHAPE= 1  MEAN= 0.1006  INT= 0.0000    2725 1451   49
   END POINT(MEV)= 0.4330  SHAPE= 1  MEAN= 0.1269  INT= 0.0053    2725 1451   50
   END POINT(MEV)= 0.4480  SHAPE= 1  MEAN= 0.1318  INT= 0.0047    2725 1451   51
   END POINT(MEV)= 0.4680  SHAPE= 2  MEAN= 0.1481  INT= 0.0000    2725 1451   52
   END POINT(MEV)= 0.4860  SHAPE= 2  MEAN= 0.1541  INT= 0.0000    2725 1451   53
   END POINT(MEV)= 0.4960  SHAPE= 1  MEAN= 0.1479  INT= 0.0013    2725 1451   54
   END POINT(MEV)= 0.5400  SHAPE= 1  MEAN= 0.1629  INT= 0.0410    2725 1451   55
   END POINT(MEV)= 0.6270  SHAPE= 0  MEAN= 0.1933  INT= 0.5430    2725 1451   56
   END POINT(MEV)= 0.6650  SHAPE= 1  MEAN= 0.2069  INT= 0.0000    2725 1451   57
   END POINT(MEV)= 0.6870  SHAPE= 1  MEAN= 0.2148  INT= 0.0400    2725 1451   58
   END POINT(MEV)= 0.6940  SHAPE= 1  MEAN= 0.2173  INT= 0.0410    2725 1451   59
   END POINT(MEV)= 0.8010  SHAPE= 1  MEAN= 0.2566  INT= 0.0010    2725 1451   60
   END POINT(MEV)= 1.1780  SHAPE= 2  MEAN= 0.3986  INT= 0.0230    2725 1451   61
   END POINT(MEV)= 1.3125  SHAPE= 1  MEAN= 0.4563  INT= 0.3000    2725 1451   62
                                                                  2725 1451   63
      MEAN GAMMA ENERGY              =    425.2035  KEV           2725 1451   64
      MEAN BETA- ENERGY              =    276.6599  KEV           2725 1451   65
      BETA- + NEUTRINO ENERGY        =    845.2753  KEV           2725 1451   66
      MEAN X-RAY ENERGY              =     16.5963  KEV           2725 1451   67
      MEAN AUGER ELECTRON ENERGY     =      2.7943  KEV           2725 1451   68
      MEAN CONVERSION ELECTRON ENERGY=     21.8027  KEV           2725 1451   69
      INTERNAL BREMSSTRAHLUNG ENERGY =      0.3023  KEV           2725 1451   70
      EFFECTIVE Q VALUE              =   1312.5000  KEV           2725 1451   71
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.1371                2725 1451   72
      CALCULATED Q VALUE             =   1311.6720  KEV           2725 1451   73
      % DEVIATION                    =      0.0631                2725 1451   74
                                                                  2725 1451   75
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).         2725 1451   76
                                1        451         78          12725 1451   77
                                8        457        439          12725 1451   78
 0.000000+0 0.000000+0          0          0          0          02725 1  099999
                                                                  2725 0  0    0
7.41870E+041.85351E+02          0          0          0          42725 8457    1
8.58600E+042.88000E+02          0          0          6          02725 8457    2
3.01257E+051.13700E+044.42102E+051.58767E+040.00000E+000.00000E+002725 8457    3
1.50000E+00-1.0000E+00          0          0          6          12725 8457    4
1.00000E+000.00000E+001.31250E+061.80000E+031.00000E+000.00000E+002725 8457    5
0.00000E+000.00000E+00          0          0          6         482725 8457    6
2.70000E-011.00000E-024.25204E+051.57897E+040.00000E+000.00000E+002725 8457    7
7.20000E+032.00000E+02          0          0         12          02725 8457    8
1.00000E+000.00000E+001.80000E-042.00000E-050.00000E+000.00000E+002725 8457    9
5.44000E+022.01280E+010.00000E+000.00000E+000.00000E+000.00000E+002725 8457   10
2.93000E+041.00000E+02          0          0         12          02725 8457   11
1.00000E+000.00000E+001.40000E-043.00000E-050.00000E+000.00000E+002725 8457   12
3.40000E+019.86000E-010.00000E+000.00000E+002.65000E+017.68500E-012725 8457   13
3.65000E+042.00000E+02          0          0         12          02725 8457   14
1.00000E+000.00000E+001.40000E-042.00000E-050.00000E+000.00000E+002725 8457   15
2.30000E+019.89000E-010.00000E+000.00000E+001.80000E+017.74000E-012725 8457   16
4.36500E+048.00000E+01          0          0         12          02725 8457   17
1.00000E+000.00000E+006.00000E-053.00000E-050.00000E+000.00000E+002725 8457   18
1.05000E+015.04000E-010.00000E+000.00000E+007.90000E+003.79200E-012725 8457   19
7.20000E+043.00000E+01          0          0         12          02725 8457   20
1.00000E+000.00000E+004.07000E-012.00000E-030.00000E+000.00000E+002725 8457   21
9.00000E-011.98000E-027.20000E-011.58400E-021.45000E-013.19000E-032725 8457   22
7.73000E+041.00000E+02          0          0         12          02725 8457   23
1.00000E+000.00000E+002.90000E-044.00000E-050.00000E+000.00000E+002725 8457   24
1.12000E+015.04000E-019.40000E+004.23000E-011.45000E+006.52500E-022725 8457   25
1.06600E+051.00000E+02          0          0         12          02725 8457   26
1.00000E+000.00000E+006.00000E-041.00000E-040.00000E+000.00000E+002725 8457   27
4.40000E+001.01200E-013.70000E+008.51000E-025.50000E-011.26500E-022725 8457   28
1.06700E+053.00000E+02          0          0         12          02725 8457   29
1.00000E+000.00000E+005.00000E-041.00000E-040.00000E+000.00000E+002725 8457   30
4.40000E+001.01200E-013.70000E+008.51000E-025.50000E-011.26500E-022725 8457   31
1.13800E+052.00000E+02          0          0         12          02725 8457   32
1.00000E+000.00000E+002.90000E-031.00000E-040.00000E+000.00000E+002725 8457   33
3.70000E+009.99000E-023.15000E+008.50500E-024.90000E-011.32300E-022725 8457   34
1.34250E+051.00000E+01          0          0         12          02725 8457   35
1.00000E+000.00000E+003.21000E-017.00000E-030.00000E+000.00000E+002725 8457   36
2.30000E+009.89000E-021.95000E+008.38500E-023.10000E-011.33300E-022725 8457   37
1.68500E+055.00000E+02          0          0         12          02725 8457   38
1.00000E+000.00000E+009.00000E-053.00000E-050.00000E+000.00000E+002725 8457   39
1.20000E+002.04000E-021.01000E+001.71700E-021.60000E-012.72000E-032725 8457   40
1.98300E+051.00000E+02          0          0         12          02725 8457   41
1.00000E+000.00000E+006.00000E-052.00000E-050.00000E+000.00000E+002725 8457   42
5.50000E-011.98000E-024.10000E-011.47600E-021.10000E-013.96000E-032725 8457   43
2.06250E+052.00000E+01          0          0         12          02725 8457   44
1.00000E+000.00000E+004.80000E-034.00000E-040.00000E+000.00000E+002725 8457   45
3.45000E+004.83000E-022.60000E+003.64000E-026.30000E-018.82000E-032725 8457   46
2.08300E+053.00000E+02          0          0         12          02725 8457   47
1.00000E+000.00000E+002.50000E-059.00000E-060.00000E+000.00000E+002725 8457   48
2.80000E-011.00800E-021.55000E-015.58000E-039.50000E-023.42000E-032725 8457   49
2.39100E+052.00000E+02          0          0         12          02725 8457   50
1.00000E+000.00000E+003.10000E-031.00000E-040.00000E+000.00000E+002725 8457   51
3.22000E-019.98200E-032.50000E-017.75000E-035.90000E-021.82900E-032725 8457   52
2.46300E+051.00000E+02          0          0         12          02725 8457   53
1.00000E+000.00000E+004.20000E-033.00000E-040.00000E+000.00000E+002725 8457   54
3.70000E-019.99000E-033.10000E-018.37000E-035.00000E-021.35000E-032725 8457   55
2.75600E+051.00000E+02          0          0         12          02725 8457   56
1.00000E+000.00000E+009.00000E-052.00000E-050.00000E+000.00000E+002725 8457   57
2.14000E-014.92200E-031.70000E-013.91000E-033.70000E-028.51000E-042725 8457   58
3.52900E+051.00000E+02          0          0         12          02725 8457   59
1.00000E+000.00000E+005.70000E-052.20000E-050.00000E+000.00000E+002725 8457   60
1.08000E-014.96800E-038.70000E-024.00200E-031.70000E-027.82000E-042725 8457   61
4.54700E+051.00000E+02          0          0         12          02725 8457   62
1.00000E+000.00000E+001.17000E-037.00000E-050.00000E+000.00000E+002725 8457   63
2.80000E-021.00800E-032.05000E-027.38000E-045.40000E-031.94400E-042725 8457   64
4.79490E+057.00000E+01          0          0         12          02725 8457   65
1.00000E+000.00000E+008.03000E-017.00000E-030.00000E+000.00000E+002725 8457   66
2.47000E-029.88000E-041.85000E-027.40000E-044.60000E-031.84000E-042725 8457   67
4.84000E+051.00000E+02          0          0         12          02725 8457   68
1.00000E+000.00000E+006.30000E-043.00000E-050.00000E+000.00000E+002725 8457   69
2.37000E-024.97700E-041.80000E-023.78000E-044.40000E-039.24000E-052725 8457   70
5.11650E+055.00000E+01          0          0         12          02725 8457   71
1.00000E+000.00000E+002.36000E-023.00000E-040.00000E+000.00000E+002725 8457   72
2.04000E-025.10000E-041.55000E-023.87500E-043.80000E-039.50000E-052725 8457   73
5.51490E+056.00000E+01          0          0         12          02725 8457   74
1.00000E+000.00000E+001.87000E-013.00000E-030.00000E+000.00000E+002725 8457   75
6.10000E-039.76000E-055.10000E-038.16000E-057.50000E-041.20000E-052725 8457   76
5.64900E+052.00000E+02          0          0         12          02725 8457   77
1.00000E+000.00000E+004.40000E-041.60000E-040.00000E+000.00000E+002725 8457   78
3.20000E-029.92000E-042.65000E-028.21500E-044.50000E-031.39500E-042725 8457   79
5.76900E+057.00000E+02          0          0         12          02725 8457   80
1.00000E+000.00000E+002.40000E-043.00000E-050.00000E+000.00000E+002725 8457   81
1.55000E-024.96000E-041.20000E-023.84000E-042.70000E-038.64000E-052725 8457   82
5.88960E+056.00000E+01          0          0         12          02725 8457   83
1.00000E+000.00000E+004.80000E-032.00000E-040.00000E+000.00000E+002725 8457   84
3.67000E-029.90900E-043.10000E-028.37000E-045.00000E-031.35000E-042725 8457   85
6.12200E+056.00000E+02          0          0         12          02725 8457   86
1.00000E+000.00000E+008.00000E-054.00000E-050.00000E+000.00000E+002725 8457   87
3.30000E-029.90000E-042.80000E-028.40000E-044.30000E-031.29000E-042725 8457   88
6.18280E+056.00000E+01          0          0         12          02725 8457   89
1.00000E+000.00000E+002.30000E-011.00000E-030.00000E+000.00000E+002725 8457   90
3.07000E-021.01310E-032.60000E-028.58000E-044.00000E-031.32000E-042725 8457   91
6.25500E+051.00000E+02          0          0         12          02725 8457   92
1.00000E+000.00000E+004.00000E-023.00000E-040.00000E+000.00000E+002725 8457   93
1.30000E-024.94000E-041.02000E-023.87600E-042.20000E-038.36000E-052725 8457   94
6.38500E+055.00000E+02          0          0         12          02725 8457   95
1.00000E+000.00000E+006.00000E-052.00000E-050.00000E+000.00000E+002725 8457   96
4.50000E-039.90000E-053.80000E-038.36000E-055.50000E-041.21000E-052725 8457   97
6.38660E+057.00000E+01          0          0         12          02725 8457   98
1.00000E+000.00000E+006.00000E-052.00000E-050.00000E+000.00000E+002725 8457   99
1.23000E-025.04300E-049.70000E-033.97700E-042.05000E-038.40500E-052725 8457  100
6.47300E+053.00000E+02          0          0         12          02725 8457  101
1.00000E+000.00000E+002.80000E-051.20000E-050.00000E+000.00000E+002725 8457  102
3.28000E-029.84000E-042.80000E-028.40000E-044.20000E-031.26000E-042725 8457  103
6.82300E+051.00000E+02          0          0         12          02725 8457  104
1.00000E+000.00000E+002.50000E-042.50000E-040.00000E+000.00000E+002725 8457  105
2.92000E-029.92800E-042.50000E-028.50000E-043.60000E-031.22400E-042725 8457  106
6.85740E+055.00000E+01          0          0         12          02725 8457  107
1.00000E+000.00000E+001.00000E+000.00000E+000.00000E+000.00000E+002725 8457  108
3.85000E-035.00500E-053.23000E-034.19900E-054.72000E-046.13600E-062725 8457  109
6.92400E+053.00000E+02          0          0         12          02725 8457  110
1.00000E+000.00000E+006.00000E-053.00000E-050.00000E+000.00000E+002725 8457  111
2.71000E-021.00270E-032.30000E-028.51000E-043.50000E-031.29500E-042725 8457  112
7.45400E+052.00000E+02          0          0         12          02725 8457  113
1.00000E+000.00000E+001.11000E-023.00000E-040.00000E+000.00000E+002725 8457  114
2.24000E-021.00800E-031.90000E-028.55000E-042.90000E-031.30500E-042725 8457  115
7.72910E+056.00000E+01          0          0         12          02725 8457  116
1.00000E+000.00000E+001.52000E-012.00000E-030.00000E+000.00000E+002725 8457  117
1.90000E-021.00700E-031.60000E-028.48000E-042.50000E-031.32500E-042725 8457  118
8.16560E+052.00000E+01          0          0         12          02725 8457  119
1.00000E+000.00000E+003.70000E-042.00000E-050.00000E+000.00000E+002725 8457  120
1.80000E-021.00800E-031.51000E-028.45600E-042.40000E-031.34400E-042725 8457  121
8.25920E+056.00000E+01          0          0         12          02725 8457  122
1.00000E+000.00000E+008.50000E-061.30000E-060.00000E+000.00000E+002725 8457  123
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002725 8457  124
8.26600E+053.00000E+02          0          0         12          02725 8457  125
1.00000E+000.00000E+008.50000E-061.30000E-060.00000E+000.00000E+002725 8457  126
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002725 8457  127
8.44700E+055.00000E+02          0          0         12          02725 8457  128
1.00000E+000.00000E+009.00000E-065.00000E-060.00000E+000.00000E+002725 8457  129
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002725 8457  130
8.64600E+051.00000E+02          0          0         12          02725 8457  131
1.00000E+000.00000E+001.24000E-022.00000E-040.00000E+000.00000E+002725 8457  132
1.56000E-022.02800E-041.30000E-021.69000E-042.20000E-032.86000E-052725 8457  133
8.79600E+052.00000E+02          0          0         12          02725 8457  134
1.00000E+000.00000E+005.20000E-031.00000E-040.00000E+000.00000E+002725 8457  135
1.48000E-022.07200E-041.25000E-021.75000E-041.90000E-032.66000E-052725 8457  136
9.60170E+055.00000E+01          0          0         12          02725 8457  137
1.00000E+000.00000E+004.80000E-053.00000E-060.00000E+000.00000E+002725 8457  138
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002725 8457  139
1.05620E+061.00000E+02          0          0         12          02725 8457  140
1.00000E+000.00000E+008.00000E-062.00000E-060.00000E+000.00000E+002725 8457  141
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002725 8457  142
1.19040E+061.00000E+02          0          0         12          02725 8457  143
1.00000E+000.00000E+008.00000E-061.00000E-060.00000E+000.00000E+002725 8457  144
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002725 8457  145
1.22080E+063.00000E+02          0          0         12          02725 8457  146
1.00000E+000.00000E+006.00000E-072.00000E-070.00000E+000.00000E+002725 8457  147
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002725 8457  148
1.23050E+065.00000E+02          0          0         12          02725 8457  149
1.00000E+000.00000E+004.80000E-055.00000E-060.00000E+000.00000E+002725 8457  150
0.00000E+000.00000E+000.00000E+000.00000E+000.00000E+000.00000E+002725 8457  151
0.00000E+001.00000E+00          0          0          6         172725 8457  152
1.00000E+000.00000E+002.76660E+051.11555E+040.00000E+000.00000E+002725 8457  153
8.20000E+042.00000E+03          0          0          6          02725 8457  154
1.00000E+001.00000E+003.50000E-051.20000E-050.00000E+000.00000E+002725 8457  155
9.20000E+042.00000E+03          0          0          6          02725 8457  156
1.00000E+001.00000E+002.00000E-071.00000E-070.00000E+000.00000E+002725 8457  157
1.22000E+052.00000E+03          0          0          6          02725 8457  158
1.00000E+001.00000E+001.30000E-044.00000E-050.00000E+000.00000E+002725 8457  159
3.52000E+052.00000E+03          0          0          6          02725 8457  160
1.00000E+001.00000E+001.50000E-051.00000E-060.00000E+000.00000E+002725 8457  161
4.33000E+052.00000E+03          0          0          6          02725 8457  162
1.00000E+001.00000E+005.30000E-033.00000E-040.00000E+000.00000E+002725 8457  163
4.48000E+052.00000E+03          0          0          6          02725 8457  164
1.00000E+001.00000E+004.70000E-031.00000E-040.00000E+000.00000E+002725 8457  165
4.68000E+052.00000E+03          0          0          6          02725 8457  166
1.00000E+002.00000E+001.90000E-057.00000E-060.00000E+000.00000E+002725 8457  167
4.86000E+052.00000E+03          0          0          6          02725 8457  168
1.00000E+002.00000E+002.40000E-051.20000E-050.00000E+000.00000E+002725 8457  169
4.96000E+052.00000E+03          0          0          6          02725 8457  170
1.00000E+001.00000E+001.30000E-032.00000E-040.00000E+000.00000E+002725 8457  171
5.40000E+052.00000E+03          0          0          6          02725 8457  172
1.00000E+001.00000E+004.10000E-021.00000E-030.00000E+000.00000E+002725 8457  173
6.27000E+052.00000E+03          0          0          6          02725 8457  174
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1.00000E+000.00000E+001.75500E-051.75500E-060.00000E+000.00000E+002725 8457  415
8.14198E+054.07099E+04          0          0          6          02725 8457  416
1.00000E+000.00000E+004.99500E-084.99500E-090.00000E+000.00000E+002725 8457  417
8.54065E+054.27032E+04          0          0          6          02725 8457  418
1.00000E+000.00000E+007.36560E-067.36560E-070.00000E+000.00000E+002725 8457  419
8.62238E+054.31119E+04          0          0          6          02725 8457  420
1.00000E+000.00000E+001.33920E-061.33920E-070.00000E+000.00000E+002725 8457  421
8.69065E+054.34532E+04          0          0          6          02725 8457  422
1.00000E+000.00000E+002.66760E-062.66760E-070.00000E+000.00000E+002725 8457  423
8.77238E+054.38619E+04          0          0          6          02725 8457  424
1.00000E+000.00000E+005.61600E-075.61600E-080.00000E+000.00000E+002725 8457  425
0.00000E+009.00000E+00          0          0          6          62725 8457  426
1.00000E+000.00000E+001.65963E+041.65963E+030.00000E+000.00000E+002725 8457  427
2.36200E+034.72400E+01          0          0          6          02725 8457  428
1.00000E+000.00000E+007.84020E-037.84020E-040.00000E+000.00000E+002725 8457  429
8.86400E+031.77280E+02          0          0          6          02725 8457  430
1.00000E+000.00000E+008.28657E-028.28657E-030.00000E+000.00000E+002725 8457  431
5.97179E+041.19436E+03          0          0          6          02725 8457  432
1.00000E+000.00000E+007.30390E-027.30390E-030.00000E+000.00000E+002725 8457  433
6.11400E+041.22280E+03          0          0          6          02725 8457  434
1.00000E+000.00000E+001.26365E-011.26365E-020.00000E+000.00000E+002725 8457  435
6.92000E+041.38400E+03          0          0          6          02725 8457  436
1.00000E+000.00000E+004.30905E-024.30905E-030.00000E+000.00000E+002725 8457  437
7.12000E+041.42400E+03          0          0          6          02725 8457  438
1.00000E+000.00000E+001.08674E-021.08674E-030.00000E+000.00000E+002725 8457  439
                                                                  2725 8  099999
                                                                  2725 0  0    0
                                                                     0 0  0    0
 7.418800+4 1.863440+2         -1          0          2          12726 1451    1
 0.000000+0 1.000000+0          0          0          0          62726 1451    2
 0.000000+0 0.000000+0          0          0          4        3112726 1451    3
 0.000000+0 0.000000+0          0          0         83          22726 1451    4
 74-W -188 HAR+WIN    EVAL-OCT05 A.L. NICHOLS                     2726 1451    5
                      DIST-NOV07                       261107     2726 1451    6
----JEFF-311          MATERIAL 2726                               2726 1451    7
-----RADIOACTIVE DECAY DATA                                       2726 1451    8
------ENDF-6 FORMAT                                               2726 1451    9
******************************************************************2726 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2726 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2726 1451   12
**             Original data taken from:  UKPADD67              **2726 1451   13
******************************************************************2726 1451   14
                                                                  2726 1451   15
     B Singh                 Nucl Data Sheets 95(2002)387         2726 1451   16
     B E Zimmerman et al     Appl Radiat Isot 56(2002)315 (T1/2)  2726 1451   17
     M P Unterweger          Appl Radiat Isot 56(2002)125 (T1/2)  2726 1451   18
     M Lindner, J S Coleman  J Am Chem Soc 73(1951)1610 (T1/2)    2726 1451   19
     J C Roy                 Can J Phys 40(1962)677               2726 1451   20
                             (T1/2, Egamma, Pgamma)               2726 1451   21
     S B Burson et al        Phys Rev  136(1964)B1                2726 1451   22
                             (Egamma, Pgamma)                     2726 1451   23
     A A Suarez et al        Nucl Phys A107(1968)417 (Pce)        2726 1451   24
     E B Shera et al         Phys Rev C6(1972)537 (nucl levels)   2726 1451   25
     T Kibedi et al          Proc Int Conf Nucl Data for Sci and  2726 1451   26
                             Technol, 26 Sept - 1 Oct 2004,       2726 1451   27
                             Santa Fe, New Mexico, USA,           2726 1451   28
                             Editors: R C Haight et al,           2726 1451   29
                             AIP Conf Proc 769 (2005) Part 1, 268 2726 1451   30
                            (ICC)                                 2726 1451   31
                                                                  2726 1451   32
The recommended half-life is dominated by an accurate and well-   2726 1451   33
defined half-life measurement of 69.78(5) days by Zimmerman et    2726 1451   34
al (2002).  Although this value was also adopted by Unterweger    2726 1451   35
(2002), one more significant figure was quoted (69.783(48)        2726 1451   36
days).                                                            2726 1451   37
                                                                  2726 1451   38
A relatively simple decay scheme has been derived primarily from  2726 1451   39
the beta and gamma-ray studies of Burson et al (1964) and Shera   2726 1451   40
et al (1972), and the conversion-electron measurements of Suarez  2726 1451   41
et al (1968).  The proposed decay scheme is based on the relative 2726 1451   42
gamma-ray emission probability measurements of Shera et al,       2726 1451   43
coupled with the derivation of the direct beta decay to the       2726 1451   44
ground state of Re-188 by Burson et al.  Mixing ratios for the    2726 1451   45
main gamma transitions were estimated from the conversion-        2726 1451   46
electron measurements of Suarez et al, although considerable      2726 1451   47
uncertainty remains with respect to the internal conversion       2726 1451   48
coefficients of the 141.76-, 227.08- and 290.67-keV gamma rays.   2726 1451   49
Beta decay occurs to the 290.67-, 207.85- and 63.58-keV nuclear   2726 1451   50
levels and the ground state of Re-188; whereas no beta decay is   2726 1451   51
assumed to occur to the 205.3-keV ((2) -) and 169.44-keV ((3) -)  2726 1451   52
nuclear levels.  One very low-intensity gamma ray proposed by     2726 1451   53
Shera et al was rejected (energy of 105.85 keV), after careful    2726 1451   54
consideration of the proposed decay scheme.  Furthermore minor    2726 1451   55
adjustments were made to the relative emission probability of the 2726 1451   56
85.32-keV gamma ray (adjusted from 0.6(2) to 0.5(2)) in order to  2726 1451   57
achieve the necessary population/depopulation balance of the      2726 1451   58
gamma transitions associated with the 205.3-keV nuclear level.    2726 1451   59
                                                                  2726 1451   60
There are some significant uncertainties associated with specific 2726 1451   61
features of the proposed decay scheme, particularly with respect  2726 1451   62
to the extent of direct beta decay to the ground state of Re-188, 2726 1451   63
and hence the derivation of the normalization factor for the      2726 1451   64
gamma-ray emission probabilities.  Further gamma-ray measurements 2726 1451   65
are required to develop and clarify the decay scheme (i.e.,       2726 1451   66
absolute gamma-ray emission probabilities).                       2726 1451   67
                                                                  2726 1451   68
                                                                  2726 1451   69
      MEAN BETA- ENERGIES:-                                       2726 1451   70
   END POINT(MEV)= 0.0580  SHAPE= 1  MEAN= 0.0149  INT= 0.0085    2726 1451   71
   END POINT(MEV)= 0.1410  SHAPE= 0  MEAN= 0.0374  INT= 0.0001    2726 1451   72
   END POINT(MEV)= 0.2850  SHAPE= 2  MEAN= 0.0888  INT= 0.0014    2726 1451   73
   END POINT(MEV)= 0.3490  SHAPE= 1  MEAN= 0.0997  INT= 0.9900    2726 1451   74
                                                                  2726 1451   75
      MEAN GAMMA ENERGY              =      1.7891  KEV           2726 1451   76
      MEAN BETA- ENERGY              =     98.9219  KEV           2726 1451   77
      BETA- + NEUTRINO ENERGY        =    346.4140  KEV           2726 1451   78
      MEAN X-RAY ENERGY              =      0.1242  KEV           2726 1451   79
      MEAN AUGER ELECTRON ENERGY     =      0.0440  KEV           2726 1451   80
      MEAN CONVERSION ELECTRON ENERGY=      0.6241  KEV           2726 1451   81
      EFFECTIVE Q VALUE              =    349.0000  KEV           2726 1451   82
      UNCERTAINTY IN EFFECTIVE Q (%) =      0.8596                2726 1451   83
      CALCULATED Q VALUE             =    348.9954  KEV           2726 1451   84
      % DEVIATION                    =      0.0013                2726 1451   85
                                                                  2726 1451   86
   ENDF-6  DATA PRODUCED BY COGEND (VERSION DATED - MAR 2004).    2726 1451   87
                                1        451         89          12726 1451   88
                                8        457         96          12726 1451   89
 0.000000+0 0.000000+0          0          0          0          02726 1  099999
 0.000000+0 0.000000+0          0          0          0          02726 0  0    0
 7.418800+4 1.863440+2          0          0          0          42726 8457    1
 6.028990+6 4.320000+3          0          0         34          02726 8457    2
 9.959000+4 8.572490+2 1.913310+3 8.637350+1 0.000000+0 0.000000+02726 8457    3
 9.892190+4 8.549630+2 0.000000+0 0.000000+0 4.401240+1 4.401240+02726 8457    4
 6.240760+2 6.240760+1 1.789100+3 8.547570+1 1.242110+2 1.242110+12726 8457    5
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02726 8457    6
 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+02726 8457    7
 0.000000+0 0.000000+0 2.474920+5 2.139030+3                      2726 8457    8
 0.000000+0 1.000000+0          0          0          6          12726 8457    9
 1.000000+0 0.000000+0 3.490000+5 3.000000+3 1.000000+0 0.000000+02726 8457   10
 0.000000+0 0.000000+0          0          0          6          62726 8457   11
 4.070000-3 1.700000-4 1.789100+3 8.547570+1 0.000000+0 0.000000+02726 8457   12
 6.358000+4 1.000000+1          0          0         12          02726 8457   13
 1.000000+0 0.000000+0 2.700000-1 4.000000-2 0.000000+0 0.000000+02726 8457   14
 3.440000+0 3.405600-1 0.000000+0 0.000000+0 2.660000+0 2.633400-12726 8457   15
 8.532000+4 1.000000+1          0          0         12          02726 8457   16
 1.000000+0 0.000000+0 5.000000-3 2.000000-3 0.000000+0 0.000000+02726 8457   17
 8.000000+0 8.000000-1 3.870000+0 3.870000-1 3.160000+0 3.160000-12726 8457   18
 1.417600+5 1.000000+1          0          0         12          02726 8457   19
 1.000000+0 0.000000+0 1.600000-2 2.000000-3 0.000000+0 0.000000+02726 8457   20
 1.820000+0 1.801800-1 1.460000+0 1.445400-1 2.800000-1 2.772000-22726 8457   21
 2.078600+5 1.000000+1          0          0         12          02726 8457   22
 1.000000+0 0.000000+0 2.000000-2 4.000000-3 0.000000+0 0.000000+02726 8457   23
 4.941000-1 1.037610-2 4.840000-1 1.016400-2 7.800000-3 1.638000-42726 8457   24
 2.270800+5 1.000000+1          0          0         12          02726 8457   25
 1.000000+0 0.000000+0 5.500000-1 2.000000-2 0.000000+0 0.000000+02726 8457   26
 4.800000-1 4.992000-2 3.900000-1 4.056000-2 6.700000-2 6.968000-32726 8457   27
 2.906700+5 1.000000+1          0          0         12          02726 8457   28
 1.000000+0 0.000000+0 1.000000+0 3.000000-2 0.000000+0 0.000000+02726 8457   29
 2.280000-1 2.302800-2 1.860000-1 1.878600-2 3.200000-2 3.232000-32726 8457   30
 0.000000+0 1.000000+0          0          0          6          42726 8457   31
 1.000000+0 0.000000+0 9.892190+4 8.549630+2 0.000000+0 0.000000+02726 8457   32
 5.800000+4 3.000000+3          0          0          6          02726 8457   33
 1.000000+0 1.000000+0 8.500000-3 3.000000-4 0.000000+0 0.000000+02726 8457   34
 1.410000+5 3.000000+3          0          0          6          02726 8457   35
 1.000000+0 1.000000+0 8.500000-5 1.600000-5 0.000000+0 0.000000+02726 8457   36
 2.850000+5 3.000000+3          0          0          6          02726 8457   37
 1.000000+0 2.000000+0 1.400000-3 5.000000-4 0.000000+0 0.000000+02726 8457   38
 3.490000+5 3.000000+3          0          0          6          02726 8457   39
 1.000000+0 1.000000+0 9.900000-1 1.000000-3 0.000000+0 0.000000+02726 8457   40
 0.000000+0 8.000000+0          0          0          6         202726 8457   41
 1.000000+0 0.000000+0 6.680890+2 6.680890+1 0.000000+0 0.000000+02726 8457   42
 2.362000+3 1.181000+2          0          0          6          02726 8457   43
 1.000000+0 0.000000+0 7.614950-3 7.614950-4 0.000000+0 0.000000+02726 8457   44
 6.703000+3 3.351500+2          0          0          6          02726 8457   45
 1.000000+0 0.000000+0 3.288860-3 3.288860-4 0.000000+0 0.000000+02726 8457   46
 1.364360+4 6.821800+2          0          0          6          02726 8457   47
 1.000000+0 0.000000+0 7.875450-5 7.875450-6 0.000000+0 0.000000+02726 8457   48
 5.267200+4 2.633600+3          0          0          6          02726 8457   49
 1.000000+0 0.000000+0 7.557380-5 7.557380-6 0.000000+0 0.000000+02726 8457   50
 5.304470+4 2.652240+3          0          0          6          02726 8457   51
 1.000000+0 0.000000+0 2.923070-3 2.923070-4 0.000000+0 0.000000+02726 8457   52
 6.121800+4 3.060900+3          0          0          6          02726 8457   53
 1.000000+0 0.000000+0 8.571420-4 8.571420-5 0.000000+0 0.000000+02726 8457   54
 7.008360+4 3.504180+3          0          0          6          02726 8457   55
 1.000000+0 0.000000+0 9.507520-5 9.507520-6 0.000000+0 0.000000+02726 8457   56
 7.478470+4 3.739240+3          0          0          6          02726 8457   57
 1.000000+0 0.000000+0 6.430600-5 6.430600-6 0.000000+0 0.000000+02726 8457   58
 8.295800+4 4.147900+3          0          0          6          02726 8457   59
 1.000000+0 0.000000+0 1.973950-5 1.973950-6 0.000000+0 0.000000+02726 8457   60
 1.312250+5 6.561240+3          0          0          6          02726 8457   61
 1.000000+0 0.000000+0 1.823360-5 1.823360-6 0.000000+0 0.000000+02726 8457   62
 1.361840+5 6.809180+3          0          0          6          02726 8457   63
 1.000000+0 0.000000+0 3.939760-5 3.939760-6 0.000000+0 0.000000+02726 8457   64
 1.393980+5 6.969900+3          0          0          6          02726 8457   65
 1.000000+0 0.000000+0 5.209600-6 5.209600-7 0.000000+0 0.000000+02726 8457   66
 1.554040+5 7.770180+3          0          0          6          02726 8457   67
 1.000000+0 0.000000+0 8.730150-4 8.730150-5 0.000000+0 0.000000+02726 8457   68
 1.973250+5 9.866240+3          0          0          6          02726 8457   69
 1.000000+0 0.000000+0 6.349200-7 6.349200-8 0.000000+0 0.000000+02726 8457   70
 2.054980+5 1.027490+4          0          0          6          02726 8457   71
 1.000000+0 0.000000+0 1.872200-7 1.872200-8 0.000000+0 0.000000+02726 8457   72
 2.165450+5 1.082720+4          0          0          6          02726 8457   73
 1.000000+0 0.000000+0 1.499800-4 1.499800-5 0.000000+0 0.000000+02726 8457   74
 2.189940+5 1.094970+4          0          0          6          02726 8457   75
 1.000000+0 0.000000+0 7.570200-4 7.570200-5 0.000000+0 0.000000+02726 8457   76
 2.247180+5 1.123590+4          0          0          6          02726 8457   77
 1.000000+0 0.000000+0 5.148550-5 5.148550-6 0.000000+0 0.000000+02726 8457   78
 2.801350+5 1.400670+4          0          0          6          02726 8457   79
 1.000000+0 0.000000+0 1.302400-4 1.302400-5 0.000000+0 0.000000+02726 8457   80
 2.883080+5 1.441540+4          0          0          6          02726 8457   81
 1.000000+0 0.000000+0 4.070000-5 4.070000-6 0.000000+0 0.000000+02726 8457   82
 0.000000+0 9.000000+0          0          0          6          62726 8457   83
 1.000000+0 0.000000+0 1.242110+2 1.242110+1 0.000000+0 0.000000+02726 8457   84
 2.362000+3 4.724000+1          0          0          6          02726 8457   85
 1.000000+0 0.000000+0 1.395820-4 1.395820-5 0.000000+0 0.000000+02726 8457   86
 8.864000+3 1.772800+2          0          0          6          02726 8457   87
 1.000000+0 0.000000+0 1.505400-3 1.505400-4 0.000000+0 0.000000+02726 8457   88
 5.971790+4 1.194360+3          0          0          6          02726 8457   89
 1.000000+0 0.000000+0 5.095880-4 5.095880-5 0.000000+0 0.000000+02726 8457   90
 6.114000+4 1.222800+3          0          0          6          02726 8457   91
 1.000000+0 0.000000+0 8.816400-4 8.816400-5 0.000000+0 0.000000+02726 8457   92
 6.920000+4 1.384000+3          0          0          6          02726 8457   93
 1.000000+0 0.000000+0 3.006390-4 3.006390-5 0.000000+0 0.000000+02726 8457   94
 7.120000+4 1.424000+3          0          0          6          02726 8457   95
 1.000000+0 0.000000+0 7.582100-5 7.582100-6 0.000000+0 0.000000+02726 8457   96
 0.000000+0 0.000000+0          0          0          0          02726 8  099999
 0.000000+0 0.000000+0          0          0          0          02726 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
 7.418900+4 1.873390+2         -1          0          2          12727 1451    1
 0.000000+0 1.000000+0          0          0          0          62727 1451    2
 0.000000+0 0.000000+0          0          0          4        3112727 1451    3
 0.000000+0 0.000000+0          0          0         18          22727 1451    4
 74-W -189 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2727 1451    5
                      DIST-NOV07                       261107     2727 1451    6
----JEFF-311          MATERIAL 2727                               2727 1451    7
-----RADIOACTIVE DECAY DATA                                       2727 1451    8
------ENDF-6 FORMAT                                               2727 1451    9
******************************************************************2727 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2727 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2727 1451   12
**             Original data taken from:  NUBASE                **2727 1451   13
******************************************************************2727 1451   14
******************************************************************2727 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2727 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2727 1451   17
                                                                  2727 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2727 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2727 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2727 1451   21
******************************************************************2727 1451   22
                                1        451         24          02727 1451   23
                                8        457          5          02727 1451   24
 0.000000+0 0.000000+0          0          0          0          02727 1  099999
                                                                  2727 0  0    0
 7.41890+04 1.87339+02          0          0          0          02727 8457    1
 6.42000+02 3.00000+01          0          0          6          02727 8457    2
 8.32666+05 0.00000+00 8.32666+05 0.00000+00 0.00000+00 0.00000+002727 8457    3
 1.50000+00-1.00000+00          0          0          6          12727 8457    4
 1.00000+00 0.00000+00 2.49800+06 0.00000+00 1.00000+00 0.00000+002727 8457    5
                                                                  2727 8  099999
                                                                  2727 0  0    0
                                                                     0 0  0    0
 7.419000+4 1.883310+2         -1          0          2          12728 1451    1
 0.000000+0 1.000000+0          0          0          0          62728 1451    2
 0.000000+0 0.000000+0          0          0          4        3112728 1451    3
 0.000000+0 0.000000+0          0          0         44          22728 1451    4
 74-W -190 ENSDF      EVAL-JUN03 CONVERSION OF ENSDF              2728 1451    5
 /ENSDF/              DIST-NOV07                       261107     2728 1451    6
----JEFF-311          MATERIAL 2728                               2728 1451    7
-----RADIOACTIVE DECAY DATA                                       2728 1451    8
------ENDF-6 FORMAT                                               2728 1451    9
******************************************************************2728 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2728 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2728 1451   12
**             Original data taken from:  ENSDF                 **2728 1451   13
******************************************************************2728 1451   14
******************************************************************2728 1451   15
* Converted from the ENSDF format by using the SDF2NDF code (1)  *2728 1451   16
*     (the CEA-Bruyeres version of the RADLST program).          *2728 1451   17
* (1) 0. Bersillon and J. Blachot, to be published.              *2728 1451   18
******************************************************************2728 1451   19
190W  DECAY 30.0 M    15                    I(min) = 0.0E+00 %    2728 1451   20
         Ex = 0.0         keV                     1 decay mode(s) 2728 1451   21
                                                                  2728 1451   22
190W B- DECAY               Q =  1270.0000 keV      70.0000       2728 1451   23
         Branching                100.0000 %         0.0000       2728 1451   24
                         Br*Q =  1270.0000 keV      70.0000       2728 1451   25
                                              0 isomeric state(s) 2728 1451   26
                                                                  2728 1451   27
Individual beta- transitions                                      2728 1451   28
Final level    end point    shape    av.energy        intensity   2728 1451   29
  319.700    950.293  70.000  0    310.000  30.000  100.000 0.000 2728 1451   30
                                                                  2728 1451   31
         Mean alpha    energy       0.0000 keV       0.0000       2728 1451   32
         Mean beta     energy     310.0000 keV      30.0000       2728 1451   33
         Mean conv. e- energy     149.3352 keV       7.6857       2728 1451   34
         Mean Auger e- energy       7.5943 keV       1.0623       2728 1451   35
         Mean gamma    energy      79.2950 keV                    2728 1451   36
         Mean X        energy      70.5279 keV       3.0881       2728 1451   37
         Mean recoil   energy       0.0069 keV       0.0005       2728 1451   38
         Mean neutrino energy     640.2932 keV      30.0000       2728 1451   39
         Mean neutron  energy       0.0000 keV       0.0000       2728 1451   40
         Total         energy    1257.0525 keV      43.7276       2728 1451   41
         Q effective             1270.0000 keV      70.0000       2728 1451   42
         diff. mode               -12.9475 keV      -1.0195 %     2728 1451   43
                                                                  2728 1451   44
         Mean e- bind. energy      83.9543 keV                    2728 1451   45
         diff. atomic              -5.8321 keV      -6.9468 %     2728 1451   46
         diff. nuclear             -7.1154 keV      -0.5603 %     2728 1451   47
                                                                  2728 1451   48
                                1        451         50          02728 1451   49
                                8        457         49          02728 1451   50
 0.000000+0 0.000000+0          0          0          0          02728 1  099999
                                                                  2728 0  0    0
 7.41900+04 1.88331+02          0          0          0          42728 8457    1
 1.80000+03 9.00000+01          0          0          6          02728 8457    2
 4.66929+05 3.09871+04 1.49823+05 7.20459+03 0.00000+00 0.00000+002728 8457    3
 0.00000+00 1.00000+00          0          0          6          12728 8457    4
 1.00000+00 0.00000+00 1.27000+06 7.00000+04 1.00000+00 0.00000+002728 8457    5
 0.00000+00 0.00000+00          0          0          6          22728 8457    6
 1.00000-02 0.00000+00 7.92950+04 6.50920+03 0.00000+00 0.00000+002728 8457    7
 1.57600+05 1.00000+02          0          0         12          02728 8457    8
 1.00000+00 0.00000+00 3.90000+01 4.00000+00 0.00000+00 0.00000+002728 8457    9
 1.45000+00 0.00000+00 1.20000+00 3.60000-02 1.94000-01 5.82000-032728 8457   10
 1.62100+05 1.00000+02          0          0         12          02728 8457   11
 1.00000+00 0.00000+00 1.10000+01 1.00000+00 0.00000+00 0.00000+002728 8457   12
 8.07000+00 0.00000+00 5.97000+00 1.79100-01 1.60000+00 4.80000-022728 8457   13
 0.00000+00 1.00000+00          0          0          6          12728 8457   14
 1.00000-02 0.00000+00 3.10000+05 3.00000+04 0.00000+00 0.00000+002728 8457   15
 9.50293+05 6.99998+04          0          0          6          02728 8457   16
 1.00000+00 1.00000+00 1.00000+02 0.00000+00 0.00000+00 0.00000+002728 8457   17
 0.00000+00 8.00000+00          0          0          6         102728 8457   18
 1.00000-02 0.00000+00 1.56929+05 7.75875+03 0.00000+00 0.00000+002728 8457   19
 6.70000+03 0.00000+00          0          0          6          02728 8457   20
 1.00000+00 0.00000+00 8.10001+01 6.66036+00 0.00000+00 0.00000+002728 8457   21
 4.70000+04 0.00000+00          0          0          6          02728 8457   22
 1.00000+00 0.00000+00 4.61127+00 2.05108+00 0.00000+00 0.00000+002728 8457   23
 8.59236+04 1.00001+02          0          0          6          02728 8457   24
 1.00000+00 0.00000+00 4.68000+01 5.00112+00 0.00000+00 0.00000+002728 8457   25
 9.04236+04 1.00001+02          0          0          6          02728 8457   26
 1.00000+00 0.00000+00 6.56700+01 6.28667+00 0.00000+00 0.00000+002728 8457   27
 1.45073+05 1.00001+02          0          0          6          02728 8457   28
 1.00000+00 0.00000+00 7.56600+00 8.08515-01 0.00000+00 0.00000+002728 8457   29
 1.49573+05 1.00001+02          0          0          6          02728 8457   30
 1.00000+00 0.00000+00 1.76000+01 1.68487+00 0.00000+00 0.00000+002728 8457   31
 1.54668+05 1.00001+02          0          0          6          02728 8457   32
 1.00000+00 0.00000+00 1.71600+00 1.83374-01 0.00000+00 0.00000+002728 8457   33
 1.56975+05 1.00001+02          0          0          6          02728 8457   34
 1.00000+00 0.00000+00 5.26500-01 5.62626-02 0.00000+00 0.00000+002728 8457   35
 1.59168+05 1.00001+02          0          0          6          02728 8457   36
 1.00000+00 0.00000+00 4.27900+00 4.09634-01 0.00000+00 0.00000+002728 8457   37
 1.61475+05 1.00001+02          0          0          6          02728 8457   38
 1.00000+00 0.00000+00 1.33100+00 1.27418-01 0.00000+00 0.00000+002728 8457   39
 0.00000+00 9.00000+00          0          0          6          42728 8457   40
 1.00000-02 0.00000+00 7.05279+04 3.08812+03 0.00000+00 0.00000+002728 8457   41
 8.65000+03 0.00000+00          0          0          6          02728 8457   42
 1.00000+00 0.00000+00 3.63913+01 4.34204+00 0.00000+00 0.00000+002728 8457   43
 5.97179+04 6.00000-01          0          0          6          02728 8457   44
 1.00000+00 0.00000+00 3.10494+01 2.33391+00 0.00000+00 0.00000+002728 8457   45
 6.11403+04 6.00000-01          0          0          6          02728 8457   46
 1.00000+00 0.00000+00 5.38119+01 4.00316+00 0.00000+00 0.00000+002728 8457   47
 6.93000+04 0.00000+00          0          0          6          02728 8457   48
 1.00000+00 0.00000+00 2.29974+01 1.74499+00 0.00000+00 0.00000+002728 8457   49
                                                                  2728 8  099999
                                                                  2728 0  0    0
                                                                     0 0  0    0
 7.419000+4 1.883310+2         -1          0          2          12729 1451    1
 2.381000+6 1.000000+0          1          1          0          62729 1451    2
 0.000000+0 0.000000+0          0          0          4        3112729 1451    3
 0.000000+0 0.000000+0          0          0         18          22729 1451    4
 74-W -190MCSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2729 1451    5
                      DIST-NOV07                       261107     2729 1451    6
----JEFF-311          MATERIAL 2729                               2729 1451    7
-----RADIOACTIVE DECAY DATA                                       2729 1451    8
------ENDF-6 FORMAT                                               2729 1451    9
******************************************************************2729 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2729 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2729 1451   12
**             Original data taken from:  NUBASE                **2729 1451   13
******************************************************************2729 1451   14
******************************************************************2729 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2729 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2729 1451   17
                                                                  2729 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2729 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2729 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2729 1451   21
******************************************************************2729 1451   22
                                1        451         24          02729 1451   23
                                8        457          5          02729 1451   24
 0.000000+0 0.000000+0          0          0          0          02729 1  099999
                                                                  2729 0  0    0
 7.41900+04 1.88331+02          1          1          0          02729 8457    1
 3.10000-03 0.00000+00          0          0          6          02729 8457    2
 0.00000+00 0.00000+00 2.38100+06 0.00000+00 0.00000+00 0.00000+002729 8457    3
 1.00000+01-1.00000+00          0          0          6          12729 8457    4
 3.00000+00 0.00000+00 2.38100+06 0.00000+00 1.00000+00 0.00000+002729 8457    5
                                                                  2729 8  099999
                                                                  2729 0  0    0
                                                                     0 0  0    0
 7.419100+4 1.893260+2         -1          0          2          12730 1451    1
 0.000000+0 1.000000+0          0          0          0          62730 1451    2
 0.000000+0 0.000000+0          0          0          4        3112730 1451    3
 0.000000+0 0.000000+0          0          0         18          22730 1451    4
 74-W -191 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2730 1451    5
                      DIST-NOV07                       261107     2730 1451    6
----JEFF-311          MATERIAL 2730                               2730 1451    7
-----RADIOACTIVE DECAY DATA                                       2730 1451    8
------ENDF-6 FORMAT                                               2730 1451    9
******************************************************************2730 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2730 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2730 1451   12
**             Original data taken from:  NUBASE                **2730 1451   13
******************************************************************2730 1451   14
******************************************************************2730 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2730 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2730 1451   17
                                                                  2730 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2730 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2730 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2730 1451   21
******************************************************************2730 1451   22
                                1        451         24          02730 1451   23
                                8        457          5          02730 1451   24
 0.000000+0 0.000000+0          0          0          0          02730 1  099999
                                                                  2730 0  0    0
 7.41910+04 1.89326+02          0          0          0          02730 8457    1
 2.00000+01 0.00000+00          0          0          6          02730 8457    2
 1.07967+06 0.00000+00 1.07967+06 0.00000+00 0.00000+00 0.00000+002730 8457    3
 1.50000+00-1.00000+00          0          0          6          12730 8457    4
 1.00000+00 0.00000+00 3.23900+06 0.00000+00 1.00000+00 0.00000+002730 8457    5
                                                                  2730 8  099999
                                                                  2730 0  0    0
                                                                     0 0  0    0
 7.419200+4 1.903190+2         -1          0          2          12731 1451    1
 0.000000+0 1.000000+0          0          0          0          62731 1451    2
 0.000000+0 0.000000+0          0          0          4        3112731 1451    3
 0.000000+0 0.000000+0          0          0         18          22731 1451    4
 74-W -192 CSN+BRC    EVAL-DEC03 G.AUDI, O.BERSILLON, J.BLACHOT + 2731 1451    5
                      DIST-NOV07                       261107     2731 1451    6
----JEFF-311          MATERIAL 2731                               2731 1451    7
-----RADIOACTIVE DECAY DATA                                       2731 1451    8
------ENDF-6 FORMAT                                               2731 1451    9
******************************************************************2731 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **2731 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **2731 1451   12
**             Original data taken from:  NUBASE                **2731 1451   13
******************************************************************2731 1451   14
******************************************************************2731 1451   15
Converted by 0. BERSILLON and J. BLACHOT (CEA, Bruyeres-le-Chatel)2731 1451   16
from the version of the NUBASE database as of 16-12-2003 (1).     2731 1451   17
                                                                  2731 1451   18
  (1) G. Audi, O. Bersillon, J. Blachot and A.H. Wapstra          2731 1451   19
      The NUBASE Evaluation of Nuclear and Decay Properties       2731 1451   20
      Nucl. Phys. A729 (2003) 3-128.                              2731 1451   21
******************************************************************2731 1451   22
                                1        451         24          02731 1451   23
                                8        457          5          02731 1451   24
 0.000000+0 0.000000+0          0          0          0          02731 1  099999
                                                                  2731 0  0    0
 7.41920+04 1.90319+02          0          0          0          02731 8457    1
 1.00000+01 0.00000+00          0          0          6          02731 8457    2
 6.86666+05 0.00000+00 6.86666+05 0.00000+00 0.00000+00 0.00000+002731 8457    3
 0.00000+00 1.00000+00          0          0          6          12731 8457    4
 1.00000+00 0.00000+00 2.06000+06 0.00000+00 1.00000+00 0.00000+002731 8457    5
                                                                  2731 8  099999
                                                                  2731 0  0    0
                                                                     0 0  0    0
