TENDL-2023 Nuclear data library
Neutron sub-library for At (Z=85) and A=229
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
file
(= the TENDL file, but up to 600 MeV)
EAF file
(European Activation File)
ACF file
(Activation File)
Processed plots
Plots of the cross sections and other quantities:
plot
Plots from PREPRO:
plot
T6 input files
acf.inp
eaf.inp
energies
gpf.inp
gpfs20.inp
gpfs60.inp
njoy.inp
talys.inp
talys.inp.0000
talys.inp.9999
tasman.inp