Activation analysis of structural materials irradiated by fusion and fission neutrons

The induced radioactivity of a few structural materials by D–T fusion neutrons and fission neutrons in a hybrid blanket have been calculated based on the fusion driven systems as the reference reactors. The neutron transport and activation calculations are done by the Monte Carlo transport code MCNP/4B and the activation inventory code FISPACT with the latest released IAEA Fusion Evaluated Nuclear Data Library (FENDL-2) and the ENDF/B-V uranium evaluated data. The effects of material types, impurities and energy spectra on the activation characteristics of materials are analyzed.