Tabulated data
  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 (s30, Evaluated Nuclear Data File, explicit channels up to 30 MeV, then MF6/MT5 up to 200 MeV)
  2. Another special ENDF file (s0, all channels in MF6/MT5 from 0 to 200 MeV, charged-particle transport, MCNP)
  3. Yet another Special ENDF file (s20, all explicit channels up to 20 MeV, then MF6/MT5 up to 200 MeV)
  4. Yet another Special ENDF file (s60, all explicit channels up to 60 MeV, then MF6/MT5 up to 200 MeV)
Processed evaluated files
Input files
  1. Nominal TALYS input file and energy file