Tabulated data (fast neutron range) |
- Tabular angular distributions (En - angle - cross section)
- Tabular gamma-ray intensities (En - Eg - cross section)
- Tabular partial cross sections to discrete levels (En - Level - cross section)
- Tabular residual cross sections (En - Residual product - cross section)
- Tabular spectra (En - Eout - particle - cross section)
- Tabular total and partial cross sections (En - cross section)
Evaluated formatted data (i.e. ENDF) |
- The TENDL file
- Pointwise cross sections at 293 K (pendf)
- ACE file at 293 K (ace and xsdir)
- Plots of the cross sections and other quantities: plot
- Plots from PREPRO: plot
- Comparison TENDL and ENDF/B-VII.1: plot
- Comparison TENDL and JEFF-3.2: plot
- Comparison TENDL and JENDL-4.0: plot
- Comparison TENDL and IRDFF-1.0: plot
- Comparison TENDL and CENDL-3.1: plot
- Processed cross sections and covariances with NJOY in 187 groups: matrix and plot
- Processed cross sections and covariances with NJOY in 44 groups: matrix and plot
- Processed cross sections and covariances with NJOY in 33 groups: matrix and plot
- Processed angular distribution and covariances with NJOY in 187 groups: matrix
- Processed angular distribution and covariances with NJOY in 187 groups: plots
- Processed angular distribution and covariances with NJOY in 33 groups: matrix
- Processed angular distribution and covariances with NJOY in 33 groups: plots
Histograms of the TALYS parameters for random files |
Random Evaluated formatted data (gzipped) |