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
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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
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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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
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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
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. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
....+....1....+....2....+....3....+....4....+....5....+....6....+....7....+....8