TENDL-2019 Nuclear data library
Triton sub-library for Tl (Z=81) and A=207
Tabulated data
Tabular angular distributions
(En - angle - 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
(s30, Evaluated Nuclear Data File, explicit channels up to 30 MeV, then MF6/MT5 up to 200 MeV)
Another special ENDF file
(s0, all channels in MF6/MT5 from 0 to 200 MeV, charged-particle transport, MCNP)
Processed evaluated files
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