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Improving Neutron Shielding Capacities of Datolite and Galena by Boron Carbide Additive for Nuclear Reactor Biological Shielding
Abstract:
Biological shielding of nuclear reactor is an important interest and diminishing the intricacy and cost of these installations is important interest. In this paper, we used Datolite and Galena minerals and boron carbide for nuclear reactor shielding aim. Datolite and Galena minerals that exist in many parts of world were used in the concrete mix design. Boron carbide is an important material for neutron absorption processes. The cross section in matter and neutron capture is utilizable causes to explain neutron shielding characteristics of samples. Neutron cross section simulations of samples have done by using a source of 14.1MeV reactor neutrons. Cross section and number of captured neutrons of each sample were estimated by using Geant4 Monte Carlo code. As a result, growing boron carbide concentration can raise cross section value of datolite and galena.
Keywords:
Datolite, Galena, boron carbide, neutron cross section, Geant4 Monte Carlo, Shielding