Barite Proportion Effect on Neutron Shielding by FLUKA Simulation Code

Concrete is the most generally used as neutron shield material as it is inexpensive and adjustable for any construction design. Radiation shielding properties of concrete may vary depending on the concrete composites. Different types of special concrete have been developed by the addition of shielding material. The neutron shielding properties of concrete containing different proportions of barite as an aggregate have been investigated. The macroscopic neutron removal cross sections have been calculated. The calculation of neutron removal cross section has been done by using FL UKA simulation code. The transmission of neutrons has been obtained as a function of thickness of concrete for all concrete types. According to the simulations results, it is clear that increasing barite proportion in the concrete decreased the neutron removal cross section. (author)