Rasoul Mehrnejad*, Abdulhalik Karabulut, Turgay Korkut, Bunyamin Aygun
Shielding of a biological type belonging to a nuclear reactor is considered one of the main issues and the lower complexity and expense of these installations are of important interest. In this paper, Galena mineral and Boron Carbide (B4C) were used to produce high-density heavy concrete. Galena minerals that are present in most regions of Iran were regarded to be applied in the concrete mix design. Boron Carbide (B4C) is regarded as a ceramic material that is efficient in order to absorb thermal neutrons as a consequence of a wide neutron absorption cross-section. Neutron shielding characteristics of samples could explain the cross-section in matter and neutron capture. Neutron cross-section measurements of samples have been done by using a source of 14.1MeV neutrons. By using Geant 4 Monte Carlo code, crosssection and neutron capture of each sample could be calculated through it. As a consequence, the cross-section value of concrete can be raised by growing boron carbide (B4C) concentration and lower neutron capture value of samples and boost the attributes of shielding.