Tabulated data
  1. Tabular angular distributions (En - angle - cross section)
  2. Tabular residual cross sections (En - Residual product - cross section)
  3. Tabular spectra (En - Eout - particle - cross section)
  4. Tabular total and partial cross sections (En - cross section)
Evaluated formatted data (i.e. ENDF)
  1. The TENDL file (Evaluated Nuclear Data File, explicit channels up to 30 MeV, then MF6/MT5 up to 200 MeV)
  2. Special ENDF file (all explicit channels up to 200 MeV)
  3. Another special ENDF file (all channels in MF6/MT5 from 0 to 200 MeV)
Processed evaluated files (i.e. ACE, AMPX)