3.17 Integral data test of FENDL-2 fusion nuclear data library with neutronic integral experiments

摘要

FENDL-2, the latest version of Fusion Evaluated Nuclear Data Library, had been developed based on selection of evaluated data from ENDF/B-VI, JENDL-3, JENDL-FF, BROND-2 and EFF-3 and distributed for benchmark analysis recently. Integral data test of FENDL-2 has been performed to qualify and validate the working library with a variety of neutronic integral experiments. Calculations and analyses of neutron leakage spectra and reaction rates have been performed with the 3-D Monte Carlo transport code MCNP and FEMDL-2 data library. The results were compared with the measured results and the results obtained previously with FENDL-1, EFF, JENDL-FF.