JAEA-Data/Code 2007-004 - Welcome to Research Group for ...

INT(2) = 0 K-member only without scattering matrix (P 0 data without matrix)
= 2 K- member only with P 0 matrix (P 0 data)
= 6 K- and P- members (P 0 and P 1 data)
=14 K-, P-, Q- members (P 0 -P 2 data)
=30 K-, P-, Q-, S- members (P 0 -P 3 data)
=62 K-, P-, Q-, S-, T- members (P 0 -P 4 data)
=126 K-,P-,Q-,S-,T-,U- members (P 0 -P 5 data)
INT(3) = 0 No self-shielding factor tabulation
= 1 Self-shielding factor tabulation
INT(4) The highest group which has self-shielding factor (=NGMINT)
INT(5) The lowest group which has self-shielding factor (=NGMAXT)
INT(6) Number of admixture cross-sections for self-shielding factor tabulation (=NSIGT)
INT(7) Number of temperatures for which the cross-sections given (=NTEMPT)
INT(8) Indicator for the selection of weighting flux type
(TEMP(i),i=1,12)
Temperature in Kelvin. Zero value is filled for TEMP(i>NTEMPT).
(SIG0(j),j=1,8) Admixture cross-sections for the self-shielding factor tabulation. Zero value is
filled for SIG0 (j>NSIGT).
XNU Constant ν-value in thermal range (not used now)
LENGTH Length of data per one-temperature
Member Kzzmc000 /NGT*(NGT+4)*NTEMPT/ or /4*NGT*NTEMPT/
The following data are repeated for t=1,NTEMPT (See above)
((σ s (g’, g, t), g’=1,NGT), g=1,NGT)
Scattering cross-sections from group g to g’
Note: Some nuclides may not have thermal scattering data. This can be
judged by INT(2) above or data length.
(σ up (g, t),g=1,NGT) Up-scattering cross-sections
(σ c (g, t),g=1,NGT) Capture cross-sections
(σ t (g, t),g=1,NGT) Total cross-sections
(σ f (g, t), g=1,NGT) Fission cross-sections
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