Modelling of neutron and photon transport in iron and concrete radiation shieldings by the Monte Carlo method

Particle accelerators and other high energy facilities produce penetrating ionizing radiation (neutrons and gamma-rays) that Must be shielded. The objective of this work was to model photon and neutron transport in various materials usually used for shielding, Such as concrete, iron, or graphite. The Monte Carlo method allows one to obtain particle flux and nuclear reaction rates by simulating individual particles and recording some aspects of their average behaviour. In this work several nuclear experiments were modelled: AVF 65 - gamma-ray beam (1-10 MeV) transport, HIMAC and ISIS 800 - high energy neutron (20800 MeV) transport in iron and concrete. Then the results were compared with experimental data.