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 spectra (En - Eout - particle - cross section)
  6. Tabular total and partial cross sections (En - cross section)
Evaluated formatted data (i.e. ENDF)
  1. The TENDL file
  2. Pointwise cross sections at 293 K (pendf)
  3. ACE file at 293 K (ace.gz and xsdir)
  4. Special ENDF file with MF32c and MF12/MT102 (so-called s20 file)
  5. EAF file (European Activation File) and associated covariances
  6. ACF file (Activation File)
Processed plots
  1. Plots of the cross sections and other quantities: plot
  2. Plots from PREPRO: plot
  3. Processed cross sections and covariances with NJOY in 187 groups: matrix and plot
  4. Processed cross sections and covariances with NJOY in 44 groups: matrix and plot
  5. Processed cross sections and covariances with NJOY in 33 groups: matrix and plot
  6. Processed angular distribution and covariances with NJOY in 187 groups: matrix
  7. Processed angular distribution and covariances with NJOY in 187 groups: plots
  8. Processed angular distribution and covariances with NJOY in 33 groups: matrix
  9. Processed angular distribution and covariances with NJOY in 33 groups: plots
T6 input files
Random Evaluated formatted data (gzipped)
    Random ENDF 1
    TALYS input 1
    Random ENDF 2
    TALYS input 2
    Random ENDF 3
    TALYS input 3
    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