Tabulated data (fast neutron range)
  1. Tabular elastic angular distributions (En - angle - cross section)
  2. Tabular (n,inl_1) angular distributions (En - angle - cross section)
  3. Tabular gamma-ray intensities (En - Eg - cross section)
  4. Tabular residual cross sections (En - Residual product - cross section)
  5. Tabular total and partial cross sections (En - cross section)
Evaluated formatted data (i.e. ENDF)
  1. The TENDL file
  2. Special ENDF file with MF12/MT102 (so-called s20 file)
  3. Special ENDF file similar to the TENDL file, but with a transition to MT5 at 60 MeV (so-called s60 file)
  4. EAF file (European Activation File) and associated covariances
  5. ACF file (Activation File)
Processed plots
  1. 101 random ENDF-6 files
  2. Plots of the cross sections and other quantities: plot
  3. Plots from PREPRO: plot
  4. Comparison TENDL and ENDF/B-VIII.0: plot
  5. Comparison TENDL and JEFF-3.3: plot
  6. Comparison TENDL and JENDL-4.0: plot
  7. Processed cross sections and covariances with NJOY in 187 groups: matrix and plot
  8. Processed cross sections and covariances with NJOY in 44 groups: matrix and plot
  9. Processed cross sections and covariances with NJOY in 33 groups: matrix and plot
T6 input files