Rubber based neutron shielding material simulation using MCNP5

Rubber-Based Neutron Shielding Material Simulation using MCNP5. The natural rubber-based neutron radiation shielding was simulated using MCNP5 computer code. The attenuation curves of natural rubber, rubber-neoprene, rubber-silicone, natural rubber+5% Vol. Gd2O2S composite, natural rubber+25% Vol. Borax, natural rubber+ 5% Vol. B4C, natural rubber+5% Vol. Li2O and natural rubber+5% Vol. Gd2O2S composite+Pb layer were made. The half-value layer (HVL) of each shielding was also calculated for both fast and thermal neutron. For the thermal neutron, the smallest HVL was obtained by using a composite of natural rubber+5% Vol. Gd2O2S i.e. 0.23 cm and the biggest was obtained for natural rubber+25% Vol. Borax i.e. 0.92 cm. on the other hand, for fast neutron, the smallest HVL was obtained for the shielding of Natural Rubber+5% Vol Gd2O2S i.e. 0.7 cm and Natural Rubber+25% Vol. Borax i.e. 1.23 cm. Photon was induced when thermal neutrons pass through the shielding of Natural Rubber+5% Vol Gd2O2S due to the (nth,ψ)