TENDL-2019 Nuclear data library
Neutron sub-library for Yb (Z=70) and A=169m
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)
The TENDL file
Special
ENDF
file with MF12/MT102 (so-called s20 file)
Processed plots
Plots of the cross sections and other quantities:
plot
Plots 1 from PREPRO:
plot
Plots 2 from PREPRO:
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
T6 input files
acf.inp
acf.inp_cov
eaf.inp
eaf.inp_cov
energies
gpf.inp
gpf.inp_cov
gpfs20.inp
gpfs20.inp_cov
gpfs60.inp
gpfs60.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)
Random
ENDF files (tgz)