Evaluation of neutron and gamma shielding performance of borated polyethylene using PHITS/MCNP Monte Carlo simulations and experimental measurements

Le résumé fourni par la source

Abstract The primary focus of this work is on data validation, particle transport code capabilities, and the impact of relative changes in hydrogen and boron concentrations on shielding characteristics. Materials for radiation shielding are essential in nuclear physics because they cover sensitive electronic equipment, people, and the environment from the damaging effects of ionising radiation. The sophisticated simulation tools speed up futuristic development, reduce the time and resources required for experimental testing, and allow for the correct forecast of an effective shielding material. This study examined the effectiveness of borated polyethylene (B-PE) as a shield against fast neutron radiation and evaluated its equivalent dose rate decrease. The B-PE slabs were exposed to neutrons and gamma using a 5 curie 241 Am − 9 Be neutron source and a 1 mCi 137 Cs gamma source, respectively. The experimental geometry was modelled in the same manner using the PHITS and MCNP programs, and an NRF-31 dosimeter was used to measure the radiation equivalent dose rates for various thicknesses of B-PE samples. The results of experimental equivalent dose rates and shielding parameters were compared with those from the PHITS and MCNP Monte Carlo Simulation codes, the results are in good agreement. Comparative research shows how the combined effects of the energy of the neutron and the doping of B, which replaces the hydrogen in polyethylene, affect the material’s shielding capacity. A different radiation field provide more confirmation that incorporating of low- Z elements does not improve gamma attenuation significantly and considered as a secondary result.

Ce résumé expose les affirmations des auteurs. BNTIC ne l’interprète pas comme une validation indépendante des résultats.