The preparation of polyethylene and mineral material composites, and experimental and theoretical (using MCNP Code) verification of their characteristics for neutron beam attenuation

In this research, attenuation of neutron flux from 252Cf source and neutron generator in collision with polyethylene shields containing different wt% of Boric acid has been studied experimentally and theoretically using MCNP Code. The results show that with changing the energy of neutron for obtaining optimum attenuation, the wt% of Boric acid should be changed. The experimental results were matched with simulation data. It has been shown that the polyethylene shields containing 15%wt boric acid the proper shield for attenuation 252Cf neutron flux. For 14MeV neutron generator flux the polyethylene with 7%wt Boric acid are reasonable. (author)