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AUTHOR(S): Roshlan Rahman Dipto, Abdus Sattar Mollah
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ABSTRACT This study presents calculation of gamma attenuation parameters for in-house developed Polyboron and Borated polyethylene shielding materials and locally available shielding materials like Pure polyethylene, water and ordinary concrete which can be used as potential radiation shielding materials. The study was carried out using GEANT4 which is a software arrangement, a combination of tools which can be used to simulate the particle transportation accurately through matter. The results were compared and in good match have been observed with the database of XCOM taking photon energy range 40 keV-20 MeV. For each energy 10000 particles were transported through the slab. Relaxation-lengths have been also calculated from obtaining linear attenuation coefficients. The obtained result shows Mass attenuation coefficient, Linear attenuation coefficient and relaxation length density of the shielding materials on the photon energy. The total Mass attenuation coefficient (ππ), Linear attenuation coefficient (ο), Half Value Layer (HVL) and Tenth Value Layer (TVL) of each material for some mostly used gamma radiation sources has been calculated. The study's findings can be used to understand how effective shielding is in reactor shielding, containment buildings, nuclear spent fuel casks and other shielding scenarios. These materials are engineered solutions intended to maximize safety, utility, and cost-effectiveness in radiation situations; they are more than merely barriers. As radiation technologies advance, it is crucial that they be continuously studied, optimized, and combined. |
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KEYWORDS Radiation; GEANT4; Polyboron; Reactor; Nuclear spent fuel cask; Gamma |
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Cite this paper Roshlan Rahman Dipto, Abdus Sattar Mollah. (2025) Comparative Study on Gamma Radiation Attenuation Parameters between In-House Developed and Locally Available Shielding Materials. International Journal of Chemistry and Chemical Engineering Systems, 10, 1-16 |
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