Development of the computational software tools to automate the computational analyses of fusion relevant benchmarks

The software tool was developed to automate the validation of the evaluated neutron cross sections
files against the benchmarks which provide the differential responses. Specifically it was implemented
for the energy and time distributions of neutrons and γ-ray spectra measured with the D-T and
$^{252}$Cf(s.f.) neutron sources and simulated by Monte Carlo code MCNP. The master script modifies the
MCNP input deck by selecting the desired evaluation, runs MCNP and compares the calculated
spectra with measured ones in user defined intervals. The criteria chi-squared, either for intervals or
for the whole measured range, was selected to judge about the performance of the evaluated cross
section data library. The application of the developed tools for the validation of the ENDF/B-VIII.0,
FENDL-3.1d, JEFF.3.3 and JENDL-4.0u libraries against the iron spherical benchmarks with $^{252}$Cf
and D-T sources has shown that JEFF-3.3 should be considered as superable over all others libraries
for the task of the neutron transport. However all tested libraries underestimate the neutron induced γ-
rays leakage from bulk iron by factor of two. ... mehrThe reliability of the validation conclusions was
strengthened by inter-comparison of the similar benchmarks but carried out in different labs.