Tabulated data
  1. Tabular residual cross sections (En - Residual product - cross section)
  2. Tabular spectra (En - Eout - particle - 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)
Processed evaluated files
  1. Plots from NJOY-PREPRO
Random data (based on random sampling of input TALYS parameters)
Evaluated formatted data (gzipped)
    Random ENDF 0
    TALYS input 0
    Random ENDF 1
    TALYS input 1
    Random ENDF 2
    TALYS input 2
    Random ENDF 3
    TALYS input 3
    Random ENDF 4
    TALYS input 4
    Random ENDF 5
    TALYS input 5
    Random ENDF 6
    TALYS input 6
    Random ENDF 7
    TALYS input 7
    Random ENDF 8
    TALYS input 8
    Random ENDF 9
    TALYS input 9
    Random ENDF 10
    TALYS input 10
    Random ENDF 11
    TALYS input 11
    Random ENDF 12
    TALYS input 12
    Random ENDF 13
    TALYS input 13
    Random ENDF 14
    TALYS input 14
    Random ENDF 15
    TALYS input 15
    Random ENDF 16
    TALYS input 16
    Random ENDF 17
    TALYS input 17