Photons Produced by Neutron Capture in Shields

The reliable determination of total dose due to a neutron source behind a shield requires the knowledge of both neutrons and generated gamma rays fluxes in the shield. Different materials are used in shielding for neutron sources and they may generate photons which lead to an increase of the radiological dose. In this study two numerical methods are used to solve the neutron transport problem and to determine the neutron flux through shields: - Monte Carlo method, - Iterative method. The generated gamma rays by neutron capture are calculated through shields of different materials. The Monte Carlo code MCNP is used to validate our own programmes. (author)