Abstract

In the study, the usability of epoxy/ilmenite (EP/IIm) composite material as a radiation shielding in many applications and a restoration/injection mortar for cracks developing in biological concrete shields was investigated. Radiation attenuation properties of EP/IIm composite material was searched out using 252Cf (100μg) neutron source and gamma spectrometer with stilbene organic scintillator. Fast neutron fluence rates and gamma fluxes were measured and displayed as energy distributions and attenuation relations. Thermal neutron fluence rates were measured using BF3 detector and displayed as attenuation relations. The experimental attenuation parameters; macroscopic effective removal cross-section ΣR (cm−1), total attenuation coefficient μ (cm−1) and macroscopic cross-section Σ (cm−1) of fast neutrons, gamma rays and thermal neutron respectively have been determined. Theoretical calculations have been achieved using MCNP-4C2 code to evaluate the concerned parameters. Also, MERCSF – N program had been used to recalculate ΣR (cm−1). The obtained experimental and theoretical results were compared, where a reasonable agreement was recognized.

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