Tabulated data (fast neutron range)
  1. Tabular angular distributions (En - angle - cross section)
  2. Tabular gamma-ray intensities (En - Eg - cross section)
  3. Tabular partial cross sections to discrete levels (En - Level - 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 and xsdir)
Processed plots
  1. Plots of the cross sections and other quantities: plot
  2. Plots from PREPRO: plot
  3. Comparison TENDL and ENDF/B-VII.1: plot
  4. Comparison TENDL and JEFF-3.2: plot
  5. Processed cross sections and covariances with NJOY in 187 groups: matrix and plot
  6. Processed cross sections and covariances with NJOY in 44 groups: matrix and plot
  7. Processed cross sections and covariances with NJOY in 33 groups: matrix and plot
  8. Processed angular distribution and covariances with NJOY in 187 groups: matrix
  9. Processed angular distribution and covariances with NJOY in 187 groups: plots
  10. Processed angular distribution and covariances with NJOY in 33 groups: matrix
  11. Processed angular distribution and covariances with NJOY in 33 groups: plots
Histograms of the TALYS parameters for random files
Random Evaluated formatted data (gzipped)
    Random ENDF 1
    TALYS input 1
    Random ENDF 2
    TALYS input 2
    Random ENDF 2
    TALYS input 2
    Random ENDF 2
    TALYS input 2
    Random ENDF 2
    TALYS input 2
    Random ENDF 2
    TALYS input 2
    Random ENDF 2
    TALYS input 2
    Random ENDF 2
    TALYS input 2