TENDL-2017 Nuclear data library
Gamma sub-library for Ho (Z=67) and A=152
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
(Evaluated Nuclear Data File, explicit channels up to 30 MeV, then MF6/MT5 up to 200 MeV)
Special ENDF file
(all explicit channels up to 200 MeV)
Another special ENDF file
(all channels in MF6/MT5 from 0 to 200 MeV)
Processed evaluated files (i.e. ACE, AMPX)
Plots from NJOY-PREPRO