Barite concrete for 252Cf spontaneous neutron shielding based on Monte Carlo computation

Recently, neutron applications as neutron imaging widespread and safety issue related to high neutron penetration is still a concern in neutron industry. Especially, the design of a structure to shield neutron requires structural stability, high-density material, and large fast-neutron removal cross-section while it must be cost-benefit evaluated and using available materials. In this regard, attention has been paid on different barite composite shielding material and their neutron attenuation property based on the Monte Carlo calculation using Particle and Heavy Ion Transport code System. Different types of material as barites aggregate, barites cement, and barites concrete were investigated to find the most appropriate for fast neutron shielding, especially spontaneous neutron emitted from the Cf-252 source. Preliminary results obtained from the geometry presented in Fig. 1 are displayed in Fig. 2. As the barite concrete has high density compared to other materials, and high removal cross-section, the dose computation throughout the geometry and in different tallies show that it is the most appropriate neutron shielding in this case. Besides, gamma radiations generated by neutron interaction are easily shielded by barite concrete. Fast neutron shielding properties obtained by Monte Carlo simulation here are comparable to the experimental value described by William J. Grantham (1961). Barite concrete fast-neutron attenuation good properties were expected as it is the material with the highest removal cross-section among the investigated compounds