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    Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites

    Source: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 001::page 12002
    Author:
    Osman, A. M.
    DOI: 10.1115/1.4054547
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In this study, the shielding parameters for isophorone diamine (IPDA) with different ratios of barite (BaSO4), boron carbide (B4C), and aluminum oxide (Al2O3) composites were theoretically investigated. The mass attenuation coefficients (μm) were calculated at the photon energy range (1 keV to 20 MeV) using the xcom program. The obtained data were used to calculate the linear attenuation coefficients (μ), relaxation lengths (λ), half value layer (HVL), and tenth value layer (TVL) for the same range of energy. For comparison, five other shielding materials, ordinary concrete, high-density polyethylene, borated polyethylene, lithium polyethylene, and water, were also studied. The macroscopic fast neutron removal cross-sections (∑R) were calculated for the selected composites. The obtained results show that the shielding parameters strongly depend on the photon energy, chemical composition, and density of the investigated materials. The dependence of mass attenuation coefficients and macroscopic fast neutron removal cross section on the chemical composition of the selected polymer composites was discussed. Barite composite is seen to be a good attenuating material; aluminum oxide composite is a reasonable attenuating behavior, while Boron composite shows a relatively weak attenuating properties. The results obtained through this work can be used to understand the behavior and shielding effectiveness of the selected polymer composites.
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      Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4288370
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    contributor authorOsman, A. M.
    date accessioned2022-12-27T23:19:11Z
    date available2022-12-27T23:19:11Z
    date copyright6/7/2022 12:00:00 AM
    date issued2022
    identifier issn2332-8983
    identifier otherners_009_01_012002.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4288370
    description abstractIn this study, the shielding parameters for isophorone diamine (IPDA) with different ratios of barite (BaSO4), boron carbide (B4C), and aluminum oxide (Al2O3) composites were theoretically investigated. The mass attenuation coefficients (μm) were calculated at the photon energy range (1 keV to 20 MeV) using the xcom program. The obtained data were used to calculate the linear attenuation coefficients (μ), relaxation lengths (λ), half value layer (HVL), and tenth value layer (TVL) for the same range of energy. For comparison, five other shielding materials, ordinary concrete, high-density polyethylene, borated polyethylene, lithium polyethylene, and water, were also studied. The macroscopic fast neutron removal cross-sections (∑R) were calculated for the selected composites. The obtained results show that the shielding parameters strongly depend on the photon energy, chemical composition, and density of the investigated materials. The dependence of mass attenuation coefficients and macroscopic fast neutron removal cross section on the chemical composition of the selected polymer composites was discussed. Barite composite is seen to be a good attenuating material; aluminum oxide composite is a reasonable attenuating behavior, while Boron composite shows a relatively weak attenuating properties. The results obtained through this work can be used to understand the behavior and shielding effectiveness of the selected polymer composites.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleCalculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites
    typeJournal Paper
    journal volume9
    journal issue1
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4054547
    journal fristpage12002
    journal lastpage12002_9
    page9
    treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 009 ):;issue: 001
    contenttypeFulltext
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