Tabulated data (fast neutron range)
  1. Tabular angular distributions (En - angle - cross section)
  2. Tabular residual cross sections (En - Residual product - cross section)
  3. Tabular total and partial cross sections (En - cross section)
Evaluated formatted data (i.e. ENDF)
  1. The TENDL file
  2. Special file (= the TENDL file, but up to 600 MeV)
  3. EAF file (European Activation File)
  4. ACF file (Activation File)
Processed plots
  1. Plots of the cross sections and other quantities: plot
  2. Plots from PREPRO: plot
T6 input files