European Journal of Materials Science and Engineering, 2021
The biological shield is very important in the nuclear power reactor, so it is necessary to study... more The biological shield is very important in the nuclear power reactor, so it is necessary to study the effect of crack on it. This work aims to study fiber composites as a radiation shielding for various purposes associated with nuclear installations, as properly as a repairing mixture for developing cracks in the biological shields of a nuclear power reactor. In this study, the MCNP-5 model of a pressurized water reactor (PWR) was used. Four different fiber composites of natural fiber (FP) (ρ= (1.373 g/ m3), fiber with lead (FPPb) (ρ=2.756 g /cm3), cement fiber (CF) (ρ=2.095 g/ m3) and cement-fiber-magnetite (CFM) (ρ =2.858 g /cm3) were used as the filler materials for cracking in the biological shield. The total mass attenuation coefficients µm for the studied composites have been calculated by the Win X-Com program of gamma-ray at an energy range from 0.15 – 20 MeV. Neutron and gamma-ray fluxes and dose rates were calculated through different distances of the reactor shields for d...
International Journal of Emerging Trends in Engineering and Development, 2018
Radiation shielding of nuclear facilities is essential for protection of people and environment d... more Radiation shielding of nuclear facilities is essential for protection of people and environment during normal operation and accidental conditions. In the present work, the standard concrete is chosen as a primary shield and five materials (Boron carbide (B 4 C), Ilmenite (FeTiO 3), Ferroboron (FeB), Galena (PbS) and Barite (BaSO 4)) have been chosen to be added separately to it with 20% in weight. We investigated the shielding parameters viz. mass attenuation coefficients m for gamma rays which computed by using Win-XCOM program, macroscopic effective removal cross-sections for fast neutrons Σ R , the absorption macroscopic cross section of neutrons Σ a , scattering macroscopic cross section of thermal Σ s thermal and epithermal Σ s epithermal neutrons, relaxation length λ and moderate ratio (MR) have been calculated theoretically for these concrete materials. The results have been shown that the concrete containing galena is suitable for gamma-rays and fast neutrons as it has large weight fraction of high-Z as compared with others, while concrete containing barite materials is the best moderator for neutrons. Also, the concrete contains B 4 C is the best for absorption of neutrons, while barite is the best materials for scattering of neutrons. This study is useful for enhancing the shielding design and radiation protection in the nuclear facilities.
In this study, three composites were investigated in terms of different photon interaction parame... more In this study, three composites were investigated in terms of different photon interaction parameters in the energy region of 0.015-15.0 MeV. The polymeric composites Epoxy/Ilmenite (EP/Ilm), Polyester/Ilmenite (CUP/Ilm) and Polyester/Magnetite (CUP/Mag) were used for various shielding purposes. The first, as well, was investigated as a restoration/injection mortar for cracks developing in biological shields. The computed parameters of photon interaction; equivalent atomic number Z eq , energy absorption buildup factor (EABF) and exposure buildup factor (EBF) were studied as afunction of incident photon energy, materials elemental composition and penetration depths up to 40 mean free paths (mfp). Both buildup factors were found to be small at low and high photon energy meanwhile their values are comparatively high in the intermediate energy region.In addition, Kerma relative to air for photon energy from 1 KeV to 20 MeV were computed and found to be dependent upon equivalent atomic numbers. In this work it was clear that filled composites offer better shielding capabilities over unfilled formulations and results of all concerned parameters revealed that loaded epoxy and polyester composites exhibited effectiveness for shielding, cracks treatment and design. The obtained data can be useful in estimating the gamma irradiation received by personnel or equipment protected by such shields in many application fields.
This study aims to design types of shielding materials to protect public and personnel from the e... more This study aims to design types of shielding materials to protect public and personnel from the effect of ionizing radiation. In this study, the increment in mass attenuation coefficientsµ m and linear attenuation coefficient µby using Lead nanoparticles material with chemical composition (93.69% Pb& 0.86% Al & 5.45% O) instead of bulk lead (Pb)and Iron (Fe) material have been investigated. Also the comparison of half value layer (HVL) for lead nanoparticles, bulk lead and Iron material was calculated. Mont Carlo simulation model (MCNP5) was provided to design a gamma radiation detector for comparison the gamma ray dose rate for Lead nanoparticles,bulk Lead and Iron material through different thickness of shield materials.It was found that Lead nanoparticles increased the amount of radiation absorbed in the material inside and as a result of which affected the radiation attenuation properties of material.The obtained result shows that mass attenuation coefficient depends on the photon energy, density of the materials and atomic number. From this study we notice that the valuesof µ m and µof Lead nanoparticles material are greater than bulk Lead and Iron material and also the values are decreasing with increasing the photon energy, and its HVL was less than bulk lead and Iron shield. The lead nanoparticles are also good shielding for gamma radiation, and it reduced the dose rate by using a smaller thickness of shield, it's less than bulk lead by (15%) and Iron materials by (30%), so it reduces the cost of the shield. The cost of lead nanoparticles reduces than cost of bulk lead by 33%. This study makes it clear that Lead nanoparticles can be beneficial to address the issues of radiation shielding cost effectiveness. Also showed that MCNP5 is an effective code on Nano size studies and standardized geometry can be useful for further investigations.
The goal of this work was investigated materials that can be used as good gamma shielding materia... more The goal of this work was investigated materials that can be used as good gamma shielding materials. In this paper a comparative study of the barium bismuth and barium lead borosilicate glass samples as radiation shielding parameters and optical properties was presented. Bismuth oxide glasses are very useful for developing as lead-free, high density and radio shielding glasses. The eleven cylindrical geometries barium bismuth and barium lead borosilicate glass samples have been prepared in different percentages and investigate for radiation shielding properties of gamma rays from, 137Cs and 60Co radioactive point sources. All glass samples have been prepared by melt-quenching method. The mass attenuation coefficients (μm) for all glass samples are measured experimentally and also calculated theoretically by WinXCom program and Monte Carlo Model MCNP-5. The mean free path (mfp), effective atomic numbers (Zeff) and the effective electron densities (Neff) have been determined for all g...
Radiation dose and shielding calculations are one of the most important functions in the field of... more Radiation dose and shielding calculations are one of the most important functions in the field of cyclotron design. A number of nuclear data inputs are required for the shielding design of medical cyclotrons which include the dose equivalent rate attenuation characteristics, the neutron-gamma source term and energy distribution. The radiation shielding form a major capital investment for any new cyclotron-based radioisotope production facility; therefore, an accurate cost-benefit analysis based on a complex multi-variant optimization technique is required for the shielding design. In this work, the main safety requirements for medical cyclotron were presented and the optimized total shielding cost is obtained using Genetic Algorithm (GA). In addition, the shielding thickness resulted from optimizing the total shielding cost is used in radiation dose calculation. It is proved that the GA can work with a large number of variables and reach the global minimum solution for the total shi...
International Journal of Hybrid Information Technology, 2016
In the present study, the linear attenuation coefficient and mass attenuation coefficient have be... more In the present study, the linear attenuation coefficient and mass attenuation coefficient have been calculated at energy range of 0.8MeV, 1MeV, 3Mev, 5MeV and 7MeV. The mass attenuation Coefficient µm has been calculated analytically for Iron material Fe (ρ= 7.87 g/cm 3) and developed material lead Pb (ρ= 11.3 g/cm 3) at photon energies [0.8 MeV to 7 MeV] using X-Com computer code. The obtained results were compared with the calculated values. The linear attenuation Coefficient µ has been calculated, its variations with photon energy were plotting. The Comparison between two materials Iron and Lead were also studied. The obtained result shows that µ and µm depends on the photon energy, density of the materials and atomic number. From this study we notice that the values of µm and µ of Lead material is greater than Iron material and also the values are decreasing with increasing the photon energy. The half value layer (HVL) and tenth value layer (TVL) of two studied materials were calculated at photon energy range of 0.8 MeV, 1MeV, 5MeV and 7MeV. The relation between this equation Ln (Io/I) and the thickness of material were calculated, so the curves show that the relation of Ln (Io/I) of Iron and Lead materials is increasing with the increasing of material thickness and the relation gives the straight line, also the comparison of this relation for Lead material is higher than Iron material. This study can also be utilized to improve the effectiveness of radiation shielding by using the developed shielding material.
This work is dedicated to figuring out robust epoxy/magnetite/boron carbide (EP/Mag/B4C) composit... more This work is dedicated to figuring out robust epoxy/magnetite/boron carbide (EP/Mag/B4C) composite for radiation attenuation at multiple applications related to nuclear installations, as well as restoration mortar for cracking developed in concrete biological shields. The mechanical properties (flexural, compressive, and impact strengths) and the physical properties (water absorption, porosity, and dry bulk density), each, have been performed to label the composite integrity for practical application. In practice, attenuation properties have been performed by using a collimated beam emitted from spontaneous fission 252Cf (100 μg) neutron source and neutron gamma spectrometer with stilbene scintillator. The pulse shape discrimination technique which would come of the zero cross over method was used to measure the fast neutron and gamma-ray spectra. Thermal neutron fluxes have been measured by using the thermal neutron detection system and the BF-3 detector. The attenuation parameters...
European Journal of Materials Science and Engineering, 2021
The biological shield is very important in the nuclear power reactor, so it is necessary to study... more The biological shield is very important in the nuclear power reactor, so it is necessary to study the effect of crack on it. This work aims to study fiber composites as a radiation shielding for various purposes associated with nuclear installations, as properly as a repairing mixture for developing cracks in the biological shields of a nuclear power reactor. In this study, the MCNP-5 model of a pressurized water reactor (PWR) was used. Four different fiber composites of natural fiber (FP) (ρ= (1.373 g/ m3), fiber with lead (FPPb) (ρ=2.756 g /cm3), cement fiber (CF) (ρ=2.095 g/ m3) and cement-fiber-magnetite (CFM) (ρ =2.858 g /cm3) were used as the filler materials for cracking in the biological shield. The total mass attenuation coefficients µm for the studied composites have been calculated by the Win X-Com program of gamma-ray at an energy range from 0.15 – 20 MeV. Neutron and gamma-ray fluxes and dose rates were calculated through different distances of the reactor shields for d...
International Journal of Emerging Trends in Engineering and Development, 2018
Radiation shielding of nuclear facilities is essential for protection of people and environment d... more Radiation shielding of nuclear facilities is essential for protection of people and environment during normal operation and accidental conditions. In the present work, the standard concrete is chosen as a primary shield and five materials (Boron carbide (B 4 C), Ilmenite (FeTiO 3), Ferroboron (FeB), Galena (PbS) and Barite (BaSO 4)) have been chosen to be added separately to it with 20% in weight. We investigated the shielding parameters viz. mass attenuation coefficients m for gamma rays which computed by using Win-XCOM program, macroscopic effective removal cross-sections for fast neutrons Σ R , the absorption macroscopic cross section of neutrons Σ a , scattering macroscopic cross section of thermal Σ s thermal and epithermal Σ s epithermal neutrons, relaxation length λ and moderate ratio (MR) have been calculated theoretically for these concrete materials. The results have been shown that the concrete containing galena is suitable for gamma-rays and fast neutrons as it has large weight fraction of high-Z as compared with others, while concrete containing barite materials is the best moderator for neutrons. Also, the concrete contains B 4 C is the best for absorption of neutrons, while barite is the best materials for scattering of neutrons. This study is useful for enhancing the shielding design and radiation protection in the nuclear facilities.
In this study, three composites were investigated in terms of different photon interaction parame... more In this study, three composites were investigated in terms of different photon interaction parameters in the energy region of 0.015-15.0 MeV. The polymeric composites Epoxy/Ilmenite (EP/Ilm), Polyester/Ilmenite (CUP/Ilm) and Polyester/Magnetite (CUP/Mag) were used for various shielding purposes. The first, as well, was investigated as a restoration/injection mortar for cracks developing in biological shields. The computed parameters of photon interaction; equivalent atomic number Z eq , energy absorption buildup factor (EABF) and exposure buildup factor (EBF) were studied as afunction of incident photon energy, materials elemental composition and penetration depths up to 40 mean free paths (mfp). Both buildup factors were found to be small at low and high photon energy meanwhile their values are comparatively high in the intermediate energy region.In addition, Kerma relative to air for photon energy from 1 KeV to 20 MeV were computed and found to be dependent upon equivalent atomic numbers. In this work it was clear that filled composites offer better shielding capabilities over unfilled formulations and results of all concerned parameters revealed that loaded epoxy and polyester composites exhibited effectiveness for shielding, cracks treatment and design. The obtained data can be useful in estimating the gamma irradiation received by personnel or equipment protected by such shields in many application fields.
This study aims to design types of shielding materials to protect public and personnel from the e... more This study aims to design types of shielding materials to protect public and personnel from the effect of ionizing radiation. In this study, the increment in mass attenuation coefficientsµ m and linear attenuation coefficient µby using Lead nanoparticles material with chemical composition (93.69% Pb& 0.86% Al & 5.45% O) instead of bulk lead (Pb)and Iron (Fe) material have been investigated. Also the comparison of half value layer (HVL) for lead nanoparticles, bulk lead and Iron material was calculated. Mont Carlo simulation model (MCNP5) was provided to design a gamma radiation detector for comparison the gamma ray dose rate for Lead nanoparticles,bulk Lead and Iron material through different thickness of shield materials.It was found that Lead nanoparticles increased the amount of radiation absorbed in the material inside and as a result of which affected the radiation attenuation properties of material.The obtained result shows that mass attenuation coefficient depends on the photon energy, density of the materials and atomic number. From this study we notice that the valuesof µ m and µof Lead nanoparticles material are greater than bulk Lead and Iron material and also the values are decreasing with increasing the photon energy, and its HVL was less than bulk lead and Iron shield. The lead nanoparticles are also good shielding for gamma radiation, and it reduced the dose rate by using a smaller thickness of shield, it's less than bulk lead by (15%) and Iron materials by (30%), so it reduces the cost of the shield. The cost of lead nanoparticles reduces than cost of bulk lead by 33%. This study makes it clear that Lead nanoparticles can be beneficial to address the issues of radiation shielding cost effectiveness. Also showed that MCNP5 is an effective code on Nano size studies and standardized geometry can be useful for further investigations.
The goal of this work was investigated materials that can be used as good gamma shielding materia... more The goal of this work was investigated materials that can be used as good gamma shielding materials. In this paper a comparative study of the barium bismuth and barium lead borosilicate glass samples as radiation shielding parameters and optical properties was presented. Bismuth oxide glasses are very useful for developing as lead-free, high density and radio shielding glasses. The eleven cylindrical geometries barium bismuth and barium lead borosilicate glass samples have been prepared in different percentages and investigate for radiation shielding properties of gamma rays from, 137Cs and 60Co radioactive point sources. All glass samples have been prepared by melt-quenching method. The mass attenuation coefficients (μm) for all glass samples are measured experimentally and also calculated theoretically by WinXCom program and Monte Carlo Model MCNP-5. The mean free path (mfp), effective atomic numbers (Zeff) and the effective electron densities (Neff) have been determined for all g...
Radiation dose and shielding calculations are one of the most important functions in the field of... more Radiation dose and shielding calculations are one of the most important functions in the field of cyclotron design. A number of nuclear data inputs are required for the shielding design of medical cyclotrons which include the dose equivalent rate attenuation characteristics, the neutron-gamma source term and energy distribution. The radiation shielding form a major capital investment for any new cyclotron-based radioisotope production facility; therefore, an accurate cost-benefit analysis based on a complex multi-variant optimization technique is required for the shielding design. In this work, the main safety requirements for medical cyclotron were presented and the optimized total shielding cost is obtained using Genetic Algorithm (GA). In addition, the shielding thickness resulted from optimizing the total shielding cost is used in radiation dose calculation. It is proved that the GA can work with a large number of variables and reach the global minimum solution for the total shi...
International Journal of Hybrid Information Technology, 2016
In the present study, the linear attenuation coefficient and mass attenuation coefficient have be... more In the present study, the linear attenuation coefficient and mass attenuation coefficient have been calculated at energy range of 0.8MeV, 1MeV, 3Mev, 5MeV and 7MeV. The mass attenuation Coefficient µm has been calculated analytically for Iron material Fe (ρ= 7.87 g/cm 3) and developed material lead Pb (ρ= 11.3 g/cm 3) at photon energies [0.8 MeV to 7 MeV] using X-Com computer code. The obtained results were compared with the calculated values. The linear attenuation Coefficient µ has been calculated, its variations with photon energy were plotting. The Comparison between two materials Iron and Lead were also studied. The obtained result shows that µ and µm depends on the photon energy, density of the materials and atomic number. From this study we notice that the values of µm and µ of Lead material is greater than Iron material and also the values are decreasing with increasing the photon energy. The half value layer (HVL) and tenth value layer (TVL) of two studied materials were calculated at photon energy range of 0.8 MeV, 1MeV, 5MeV and 7MeV. The relation between this equation Ln (Io/I) and the thickness of material were calculated, so the curves show that the relation of Ln (Io/I) of Iron and Lead materials is increasing with the increasing of material thickness and the relation gives the straight line, also the comparison of this relation for Lead material is higher than Iron material. This study can also be utilized to improve the effectiveness of radiation shielding by using the developed shielding material.
This work is dedicated to figuring out robust epoxy/magnetite/boron carbide (EP/Mag/B4C) composit... more This work is dedicated to figuring out robust epoxy/magnetite/boron carbide (EP/Mag/B4C) composite for radiation attenuation at multiple applications related to nuclear installations, as well as restoration mortar for cracking developed in concrete biological shields. The mechanical properties (flexural, compressive, and impact strengths) and the physical properties (water absorption, porosity, and dry bulk density), each, have been performed to label the composite integrity for practical application. In practice, attenuation properties have been performed by using a collimated beam emitted from spontaneous fission 252Cf (100 μg) neutron source and neutron gamma spectrometer with stilbene scintillator. The pulse shape discrimination technique which would come of the zero cross over method was used to measure the fast neutron and gamma-ray spectra. Thermal neutron fluxes have been measured by using the thermal neutron detection system and the BF-3 detector. The attenuation parameters...
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Papers by Amal EL-Sawy