TENDL-2021 Nuclear data library
Neutron sub-library for U (Z=92) and A=234
Tabulated data (fast neutron range)
Tabular elastic angular distributions
(En - angle - cross section)
Tabular (n,inl_1) angular distributions
(En - angle - cross section)
Tabular gamma-ray intensities
(En - Eg - 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)
EAF file
(European Activation File) and associated
covariances
ACF file
(Activation File)
Processed plots
11 random ENDF-6
files
Plots of the cross sections and other quantities:
plot
Plots from PREPRO:
plot
Comparison TENDL and ENDF/B-VIII.0:
plot
Comparison TENDL and JEFF-3.3:
plot
Comparison TENDL and JENDL-4.0:
plot
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.0004
talys.inp.0005
talys.inp.0006
talys.inp.0007
talys.inp.0008
talys.inp.0009
talys.inp.0010
talys.inp.9999
tasman.inp