Study of concrete additives to improve its protective role against neutron radiation by using MCNPX code

With the development of nuclear technology in the world and the use of the technology in industry and medical centers¡ the countries in this category¡ and investment in this area has increased. Because of nuclear-radiation such as gamma and neutron radiation¡ and also such harmful to human health¡ in these centers to avoid irreversible effects of this type of radiation¡ shielding that must be made in addition to decrease of energy and intensity of this type of radiation¡ the economy well. In design of this type of shieldings¡ role of the structural concrete must also be considered. Therefore¡ in order to provide the two things mentioned¡ the mind is focused on researchers to produce concrete with protective properties. Concrete is a substance that has highest applicaton and consumption in the world after water. Production of concrete with protective properties can be a great service to humanity. In this study¡ we have tried to use the MCNPX code for identifying additiinal material such as boron and hydrogen¡ to produce concrete protective properties¡ and investigated the treat of this kind of concrete against neutron radiation by adding materials such as polyethylene and boron carbide . In this context¡ neutron sources of Department of Energy Engineering and Physics of Amirkabir University of Technology simulated and the results show a declining trend of neutron flux with increase of the percentage of polyethylene and boron carbide in concrete.