Analysis of integral experiments on stainless steel shields for the validation of the FENDL library

The present paper describes the analysis of integral experiments on stainless steel (SS) and SS/water shielding assemblies, irradiated with 14-MeV neutrons. The analysis is performed with the Monte Carlo transport code MCNP-4A and using the Fusion Evaluated Nuclear Data Library (FENDL). The ratios of calculated over measured quantities are given and discussed for the validation of the FENDL library in view of its use in the design of the International Thermonuclear Experimental Reactor (ITER). The analysis is also done using the European Fusion File (EFF), versions 1 and 2, for comparison. The results show that these libraries can satisfactorily describe the features of the neutron and gamma radiation attenuation in large SS shields. Some trends are, however, found to underestimate the fast neutron flux (E > ≈ 0.5 MeV) in deep locations, that may lead to a non-correct evaluation of damage parameters for structural components in the reactor design.