$Rev:: 584      $  $Date:: 2011-12-19#$                             1 0  0    0
 3.009000+3 8.949250+0         -1          0          2          1  22 1451    1
 0.000000+0 1.000000+0          0          0          0          6  22 1451    2
 0.000000+0 0.000000+0          1          0          4          7  22 1451    3
 0.000000+0 0.000000+0          0          0         48          2  22 1451    4
  3-Li-  9 HAR+WIN    EVAL-APR92 A.L. NICHOLS                       22 1451    5
                      DIST-NOV07                       20111222     22 1451    6
----ENDF/B-VII.1      MATERIAL   22                                 22 1451    7
-----RADIOACTIVE DECAY DATA                                         22 1451    8
------ENDF-6 FORMAT                                                 22 1451    9
******************************************************************  22 1451   10
**             JEFF-3.11 Radioactive Decay Data File            **  22 1451   11
**          Compiled for the NEA Data Bank - Nov 2007           **  22 1451   12
**             Original data taken from:  UKPADD67              **  22 1451   13
******************************************************************  22 1451   14
      F.AJZENBERG-SELOVE            NUCL PHYS A320(1979)1           22 1451   15
      F.AJZENBERG-SELOVE            NUCL PHYS A413(1984)1           22 1451   16
      F.AJZENBERG-SELOVE            NUCL PHYS A490(1988)1           22 1451   17
      Y.S.CHEN ET AL                NUCL PHYS A146(1970)136         22 1451   18
      T.BJORNSTAD ET AL             NUCL PHYS A359(1981)1           22 1451   19
      M.LANGEVIN ET AL              NUCL PHYS A366(1981)449         22 1451   20
                                                                    22 1451   21
          LI-9 UNDERGOES BETA DECAY TO THE GROUND STATE OF          22 1451   22
      BE-9(STABLE) AND A NUMBER OF EXCITED LEVELS OF BE-9 THAT      22 1451   23
      UNDERGO SUBSEQUENT DECAY VIA DELAYED NEUTRON EMISSION.        22 1451   24
      WHILE ALL OF THE BETA-PARTICLE TRANSITIONS ARE LISTED IN      22 1451   25
      THE DATA FILE, THERE ARE A NUMBER OF DIFFICULTIES IN          22 1451   26
      DEFINING THE FULL DECAY OF THE EXCITED LEVELS OF BE-9.        22 1451   27
      DETAILED FEATURES OF THE DELAYED NEUTRON EMISSIONS HAVE       22 1451   28
      BEEN REPORTED BY LANGEVIN ET AL (2429 AND 2780KEV LEVEL       22 1451   29
      DECAYS SPLIT INTO 0.02 AND 0.32, AND 0.03 AND 0.07 TO THE     22 1451   30
      GROUND AND ILL-DEFINED EXCITED STATES OF BE-8 RESPECTIVELY),  22 1451   31
      HENCE CANNOT BE LISTED IN SUCH DETAIL IN ENDF FORMAT.         22 1451   32
          IT SHOULD ALSO BE NOTED THAT BE-8 DECAYS VIA ALPHA        22 1451   33
      EMISSION (CONTAINED WITHIN BE-8 DATA FILE).                   22 1451   34
                                                                    22 1451   35
                                                                    22 1451   36
      MEAN BETA- ENERGIES:-                                         22 1451   37
   END POINT(MEV)= 2.3200  SHAPE= 0  MEAN= 0.9962  INT= 0.0400      22 1451   38
   END POINT(MEV)= 5.6700  SHAPE= 0  MEAN= 2.6239  INT= 0.0150      22 1451   39
   END POINT(MEV)=10.8300  SHAPE= 0  MEAN= 5.1776  INT= 0.1000      22 1451   40
   END POINT(MEV)=11.1770  SHAPE= 0  MEAN= 5.3497  INT= 0.3400      22 1451   41
   END POINT(MEV)=13.6060  SHAPE= 0  MEAN= 6.5550  INT= 0.5050      22 1451   42
                                                                    22 1451   43
      MEAN BETA- ENERGY              =   5696.2510  KEV             22 1451   44
      BETA- + NEUTRINO ENERGY        =  11932.0596  KEV             22 1451   45
      INTERNAL BREMSSTRAHLUNG ENERGY =     29.8957  KEV             22 1451   46
                                                                    22 1451   47
      DECAY SCHEME IS INCOMPLETE : LACK OF NEUTRON DATA             22 1451   48
      MEAN ENERGIES DERIVED FROM THE                                22 1451   49
      PARTIAL DECAY SCHEME                                          22 1451   50
                                                                    22 1451   51
   ENDF/B-VI DATA PRODUCED BY COGEND (A.TOBIAS DEC-1990).           22 1451   52
                                1        451         54          1  22 1451   53
                                8        457         18          1  22 1451   54
 0.000000+0 0.000000+0          0          0          0          0  22 1  099999
                                                                    22 0  0    0
3.00900E+038.94925E+00          0          0          0          1  22 8457    1
1.78300E-014.00000E-04          0          0          6          0  22 8457    2
5.69625E+064.04566E+052.98957E+042.98957E+030.00000E+000.00000E+00  22 8457    3
1.50000E+00-1.0000E+00          0          0         12          2  22 8457    4
1.00000E+000.00000E+001.36060E+072.00000E+035.05000E-015.00000E-02  22 8457    5
1.50000E+000.00000E+001.19410E+073.00000E+034.95000E-015.00000E-02  22 8457    6
0.00000E+001.00000E+00          0          0          6          5  22 8457    7
1.00000E+000.00000E+005.69625E+064.04566E+050.00000E+000.00000E+00  22 8457    8
2.32000E+063.00000E+04          0          0          6          0  22 8457    9
1.00000E+001.00000E+004.00000E-025.00000E-030.00000E+000.00000E+00  22 8457   10
5.67000E+068.20000E+04          0          0          6          0  22 8457   11
1.00000E+001.00000E+001.50000E-025.00000E-030.00000E+000.00000E+00  22 8457   12
1.08300E+071.22000E+05          0          0          6          0  22 8457   13
1.00000E+001.00000E+001.00000E-012.00000E-020.00000E+000.00000E+00  22 8457   14
1.11770E+073.00000E+03          0          0          6          0  22 8457   15
1.00000E+001.00000E+003.40000E-014.00000E-020.00000E+000.00000E+00  22 8457   16
1.36060E+072.00000E+03          0          0          6          0  22 8457   17
1.00000E+001.00000E+005.05000E-015.00000E-020.00000E+000.00000E+00  22 8457   18
                                                                    22 8  099999
                                                                    22 0  0    0
 0.000000+0 0.000000+0          0          0          0          0   0 0  0    0
                                                                    -1 0  0    0
                                                                    -1 0  0    0