TENDL-2017 Nuclear data library
Neutron sub-library for Sn (Z=50) and A=100
Tabulated data (fast neutron range)
Tabular elastic angular distributions
(En - angle - cross section)
Tabular (n,inl_1) angular distributions
(En - angle - cross section)
Tabular gamma-ray intensities
(En - Eg - 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)
ENDF file (Evaluated Nuclear Data File): processing failed
ACF file
(Activation File)
Processed plots
Plots of the cross sections and other quantities:
plot
Plots from PREPRO:
plot
T6 input files
acf.inp
acf.inp_cov
energies
gpfs20.inp_cov
njoy.inp
talys.inp
talys.inp.0000
talys.inp.0001
talys.inp.0002
talys.inp.0003
talys.inp.0004
talys.inp.0005
talys.inp.0006
talys.inp.9999
tasman.inp
Random Evaluated formatted data (gzipped)