Format of JNDC FP Decay Data File Verison 2

Card ID
    #1  Title & Date card (18A4)
          Comment card and generation date of file 
    #2  Option card (12I5)
          NMAX,NPAR,NFIS,NGS ,NEUT,KSC ,NAN ,IMW ,IERR
           NMAX : Number of nuclides
           NPAR : Maximum number of parent nuclides
           NFlS : Maximum number of fission yields
           NGS  : Maximum number of energy group of neutron
                  capture cross section
           NEUT : Kind of neutron cross sections
           KSC  : Number of capture cross section nuclides
           NAN  : Number of mass number 
           IMW  : Words of comment card for library file
                   1 card (18 words)
                   2 cards(36 words)
           IERR : Kind of nuclear data library
                   = 0 nuclear data library
                   = 1 nuclear uncertainty data library
    #3  File title card (18A4)
          Comment of nuclear data library file
    #4  Fission yield code ID card (9I8)
          (NFTYP(I),I=1,NFIS) : Fission yield code
           = 9O2322(232Th(F))     = 9O2323(232Th(HE))
           = 922331(233U(T))      = 922332(233U(F))
           = 922333(233U(HE))     = 922351(235U(T))
           = 922352(235U(F))      = 922353(235U(HE))
           = 922362(236U(F))      = 922382(238U(F))
           = 922383(238U(HE))     = 932372(237Np(F))
           = 942391(239Pu(T))     = 942392(239Pu(F))
           = 942393(239Pu(HE))    = 9424O2(240Pu(F))
           = 942411(241Pu(T))     = 942412(241Pu(F)
           = 942422(242Pu(F))     = 98252O(252Cf(S))
    #5  Mass number card (9I8)
          (MASSN(I),I=1,NAN)    : Mass number 
           [Mass number 66 to 172]
    #6  Mass yield card (6E12.5)
          ((ANY(I,J),I=1,NFIS),J=1,NAN)    : Mass yield 
    #7  Nuclear data card (I6, E11.4,1X,A1,4E11.4,F5.1,2I2)
          NUCL,RAM,NU,Q,EB,EG,EA,SO,ISGC,NCH
           NUCL : Nuclear ID number
                  NUCL = Z*10000 + A*10 + IS
                          Z : Atomic number
                          A : Mass number
                          IS: State identifier
                               0 = Grand state
                               1 = Meta-stable state(M)
                               2 = Meta-stable statet(N)
           RAM  : Decay constant or half-life
           NU   : Unit of half-life
                   = blank : Decay constant
                   = S     : Second
                   = M     : Minutes
                   = H     : Hour
                   = D     : Day
                   = Y     : Year
           Q    : Q-value(Mev)
           EB   : Average beta and conversion electron energy(Mev)
           EG   : Average gamma energy(Mev)
           EA   : Average alpha energy(Mev)
           SP   : Spin data(example -2.5 : 5/2-)
           ISGC : Flag for neutron capture cross section
                   = 0 No capture cross section
                   = 1 Capture cross section
           NCH  : Number of parent nuclides
    #8  Decay types and branching ratios card (6(I3,F8.5,1X))
          (NBIC(I),PBIC(I),I=1,NCH)
           NBIC : Decay type
                  NMM   N : State identifier of parent
                             = 0 Grand state
                               1 Meta-stable state(M)
                               2 Meta-stable state(N)
                       MM : Decay type 
                             = 1 - -decay
                               2 Isomeric transition
                               3 Neutron capture reaction
                               4 + and/or electron capture dccay
                               5 -decay
                               6 Delayed neutron emission
           PBlC : Branching ratio
    #9  Independent fission yield card (6E12.5)
          (YI(I),I=1,NFlS)    : Independent fission yield
   #10  Cumulative fission yield card (6E12.5)
          (YC(I),I=1,NFIS)    : Cumulative fission yield
   #11  Neutron capture cross sections card (6E12.5) [in the case of ISGC=1]
          (SC(I),I=1,NGS)      : Neutron capture cross section
                     I = 1 ` 25  Cross sections of fast energy
                           26     Resonance integral of neutron capture reaction
                           27     Thermal neutron capture cross section for 
                                  22OO m/sec neutrons
                           28     g-factor

[Example]

....+....1....+....2....+....3....+....4....+....5....+....6....+....7....+....8   ID  Description 
LIBRARY  DATA : COPIED 90/07/26                                                    #1  Title & Date
 1227    6   20   28    1  166  107   18    0                                      #2  Option card
 JNDC FP DECAY FILE V.2 WITH CAPTURE SIG.                                          #3  File title
  902322  902323  922331  922332  922333  922351  922352  922353  922362   00010   #4  Fission yield code
  922382  922383  932372  942391  942392  942393  942402  942411  942412   00020       code ID
  942422  982520                                                        00000030
      66      67      68      69      70      71      72      73      74   00040   #5  Mass number
      75      76      77      78      79      80      81      82      83   00050
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
     156     157     158     159     160     161     162     163     164   00140
     165     166     167     168     169     170     171     172        00000150
 1.21673E-06 1.29096E-04 2.63109E-07 4.50630E-07 6.67707E-04 7.62318E-08   66010   #6  Mass yield
 8.81737E-07 3.01656E-04 7.47461E-07 1.74947E-08 8.50891E-05 1.90870E-07   66020
 1.84292E-07 8.80570E-07 6.33383E-05 5.41350E-06 1.35288E-07 1.84035E-07   66030
 1.89368E-07 2.32189E-09                                                00066040
 4.19387E-06 2.19860E-04 1.19495E-06 1.79850E-06 1.51954E-03 3.91331E-07   67010
 2.83513E-06 6.74050E-04 1.86837E-06 6.06170E-08 1.39923E-04 3.81017E-07   67020
 3.68048E-07 2.90989E-06 9.99120E-05 8.12143E-06 2.51492E-07 1.29036E-06   67030
 3.78141E-07 1.15984E-08                                                00067040
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
 1.15693E-08 1.60145E-06 1.66753E-09 2.34121E-09 4.45554E-05 5.91680E-09  170010
 2.04193E-08 3.26341E-05 8.95452E-08 6.82498E-08 6.05987E-05 4.21956E-07  170020
 3.94048E-07 9.75259E-06 4.76571E-05 3.20348E-05 1.52873E-06 1.51942E-05  170030
 4.59435E-05 1.28134E-03                                                00170040
 5.03625E-09 7.51679E-07 5.55350E-10 7.19219E-10 2.46406E-05 2.81776E-09  171010
 7.16668E-09 1.76804E-05 2.95122E-08 1.91105E-08 3.35607E-05 1.25203E-07  171020
 1.88836E-07 3.25882E-06 3.76282E-05 1.77539E-05 2.87110E-07 5.32270E-06  171030
 2.55167E-05 5.98813E-04                                                00171040
 2.59343E-09 3.49650E-07 1.85244E-10 2.69983E-10 1.89245E-05 9.70653E-10  172010
 2.04811E-09 1.60920E-05 7.93971E-09 9.98000E-09 2.16190E-05 4.84057E-07  172020
 5.55978E-08 9.65932E-07 1.88655E-05 1.03637E-05 9.58010E-08 1.52001E-06  172030
 1.53329E-05 3.76327E-04                                                00172040
230660 1.8734E+02   1.6214E+01 5.4830E+00 4.7990E+00 0.0         0.0 0 023066011   #7  Nuclear data
 2.53931E-13 3.85499E-12 2.74046E-17 5.79769E-17 5.31656E-14 1.93964E-1623066013   #9  Independent 
 9.72948E-15 1.26557E-13 1.75496E-14 6.77534E-15 1.21107E-11 3.74634E-1623066023       fission yield
 3.86294E-17 3.68364E-16 1.77382E-15 1.08924E-14 2.74879E-15 3.16130E-1523066033
 4.08893E-15 3.49802E-18                                                23066043
 2.53931E-13 3.85499E-12 2.74046E-17 5.79769E-17 5.31656E-14 1.93964E-1623066014  #10  Cumulative  
 9.72948E-15 1.26557E-13 1.75496E-14 6.77534E-15 1.21107E-11 3.74634E-1623066024       fission yield
 3.86294E-17 3.68364E-16 1.77382E-15 1.08924E-14 2.74879E-15 3.16130E-1523066034
 4.08893E-15 3.49802E-18                                                23066044
240660 2.5941E+00   9.8500E+00 3.8630E+00 1.6930E+00 0.0         0.0 0 124066011
  1 1.00000                                                             24066012   #8  Decay types and 
 4.69088E-09 9.89976E-08 1.05956E-11 1.80001E-11 1.54000E-08 2.10951E-1124066013       branching ratios
 4.88771E-10 1.93009E-08 6.47975E-10 9.55051E-11 1.56014E-07 2.97000E-1124066023
 1.05034E-11 6.95207E-11 7.55040E-10 1.35012E-09 1.16030E-10 1.27991E-1024066033
 2.22999E-10 6.51650E-14                                                24066043
 4.69113E-09 9.90014E-08 1.05956E-11 1.80002E-11 1.54001E-08 2.10953E-1124066014
 4.88781E-10 1.93010E-08 6.47993E-10 9.55119E-11 1.56026E-07 2.97004E-1124066024
 1.05034E-11 6.95211E-11 7.55042E-10 1.35013E-09 1.16033E-10 1.27994E-1024066034
 2.23003E-10 6.51685E-14                                                24066044
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
340740 0.0          0.0        0.0        0.0        0.0         0.0 1 134074011
  1 0.34900                                                             34074012
 5.93826E-18 1.28018E-15 3.67871E-14 2.23840E-13 1.91002E-12 1.14398E-1634074013
 5.79323E-16 1.49474E-13 2.82312E-16 1.85193E-19 1.80175E-16 2.17128E-1534074023
 1.14361E-14 2.45811E-14 1.07006E-12 3.15588E-15 2.60578E-17 2.45130E-1634074033
 3.82615E-18 1.80396E-16                                                34074043
 2.62539E-13 1.47281E-10 8.42509E-10 1.31938E-09 1.70647E-08 8.91849E-1234074014
 1.27611E-11 3.12032E-09 6.74282E-12 9.99338E-15 8.81037E-12 3.76938E-1134074024
 1.09210E-10 2.43342E-10 7.36539E-09 2.47137E-11 6.10301E-13 6.74250E-1234074034
 8.08859E-14 2.13058E-12                                                34074044
 3.20850E-03 1.00916E-02 1.87879E-02 2.93373E-02 4.29705E-02 7.28995E-0234074015  #11  Neutron capture 
 7.59055E-02 9.24381E-02 1.39332E-01 2.22931E-01 3.39608E-01 4.80488E-0134074025       cross sections
 6.54952E-01 2.81436E+00 4.17653E-02 2.10211E+01 4.71615E-01 7.26950E-0134074035
 7.04932E+02 1.31955E+01 5.21381E+00 5.54257E+00 7.15141E+00 9.87754E+0034074045
 2.71939E+01 5.77770E+02 5.19980E+01 1.00520E+00                        34074055
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
....+....1....+....2....+....3....+....4....+....5....+....6....+....7....+....8