TENDL-2023 Nuclear data library
Neutron sub-library for Ir (Z=77) and A=186
Tabulated data (fast neutron range)
Tabular angular distributions
(En - angle - cross section)
Tabular residual cross sections
(En - Residual product - cross section)
Tabular total and partial cross sections
(En - cross section)
Evaluated formatted data (i.e. ENDF)
The TENDL file
Special
ENDF
file with MF12/MT102 (so-called s20 file)
Special
ENDF
file similar to the TENDL file, but with a transition to MT5 at 60 MeV (so-called s60 file)
Special
file
(= the TENDL file, but up to 600 MeV)
EAF file
(European Activation File) and associated
covariances
ACF file
(Activation File)
Processed plots
Plots of the cross sections and other quantities:
plot
Plots from PREPRO:
plot
Processed cross sections and covariances with NJOY in 187 groups:
matrix
T6 input files
acf.inp
acf.inp_cov
eaf.inp
eaf.inp_cov
energies
gpf.inp
gpf.inp_cov
gpfs20.inp
gpfs20.inp_cov
gpfs60.inp
gpfs60.inp_cov
njoy.inp
talys.inp
talys.inp.0000
talys.inp.0001
talys.inp.0002
talys.inp.0003
talys.inp.9999
tasman.inp