Comparative study of different concrete composition as gamma-ray shielding materials

Waly, El-Sayed A.; Bourham, Mohamed

doi:10.1016/j.anucene.2015.05.011

Cited by 133 publications

(38 citation statements)

References 13 publications

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“…There was no comparable study in the literature on this regard. However, our finding was in accordance with results of similar studies [10,16,19,21].…”

Section: Resultssupporting

confidence: 81%

“…Cross-section library files for neutrons and photons including ENDF/B-VII and ENDF/B-VI data were used in the MC simulations. Five high-density concretes with the densities ranging from 5.11 g/cm 3 to 3.45 g/cm 3 and ordinary concrete with density of 2.3 g/cm 3 were studied in our simulations [2,3,6,19]. The compositions of the studied concretes are shown in Table 1.…”

Section: Methodsmentioning

confidence: 99%

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Neutron and photon scattering properties of high density concretes used in radiation therapy facilities: A Monte Carlo study

Mesbahi

Khaldari

2017

Polish Journal of Medical Physics and Engineering

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In the current study the neutron and photon scattering properties of some newly developed high density concretes (HDCs) were calculated by using MCNPX Monte Carlo code. Five high-density concretes including Steel-Magnetite, Barite, Datolite-Galena, Ilmenite-ilmenite, Magnetite-Lead with the densities ranging from 5.11 g/cm 3 and ordinary concrete with density of 2.3 g/cm 3 were studied in our simulations. The photon beam spectra of 4 and 18 MV fromVarian linac and neutron spectra of clinical 18 MeV photon beam was used for calculations. The fluence of scattered photon and neutron from all studied concretes was calculated in different angles. Overall, the ordinary concrete showed higher scattered photons and Datolite-Galena concrete (4.42 g/cm 3 ) had the lowest scattered photons among all studied concretes. For neutron scattering, fluence at the angle of 180 was higher relative to other angles while for photons scattering fluence was maximum at 90 degree. The scattering fluence for photons and neutrons was dependent on the angle and composition of concrete. The results showed that the fluence of scattered photons and neutrons changes with the composition of high density concrete. Also, for high density concretes, the variation of scattered fluence with angle was very pronounced for neutrons but it changed slightly for photons. The results can be used for design of radiation therapy bunkers.

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“…There was no comparable study in the literature on this regard. However, our finding was in accordance with results of similar studies [10,16,19,21].…”

Section: Resultssupporting

confidence: 81%

Section: Methodsmentioning

confidence: 99%

Neutron and photon scattering properties of high density concretes used in radiation therapy facilities: A Monte Carlo study

Mesbahi

Khaldari

2017

Polish Journal of Medical Physics and Engineering

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“…In the comparison of polymer panels it can be seen that the highest value of attenuation coefficient has been found for undoped polymer and the lowest value for barite-doped polymer panel. Barite-doped polymer panel can provide more efficient γ-ray shielding, when compared to others [4,25].…”

Section: Radiation Testsmentioning

confidence: 99%

“…Exposure to gamma rays can occur because of nuclear applications, such as reactors, nuclear research and medical diagnostic centers, and nuclear waste storage sites. It is essential to reduce the intensity of external radiation to the standard acceptable level, and hence the attenuation property of a shielding material is of great importance [4].…”

Section: Introductionmentioning

confidence: 99%

Production of Barite and Boroncarbide Doped Radiation Shielding Polymer Composite Panels

Evcin

Bezir

et al. 2017

Acta Phys. Pol. A

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Developments in nuclear technology in the last century have lead to the use of radiation in different areas of human activity. These are not just the energetics but also food, agriculture, medicine, industry and science. Thus, radiation has become an inevitable phenomenon in our lives. Since we cannot isolate radiation from our life, the radiation protection methods should be available. As alternatives to conventional radiation prevention methods, such as lead and heavy concrete shielding, more functional materials need to become the focus of research. The development of the least harmful to the environment, easily applicable, flexible radiation shields has become very important. In this study, silicon matrix composite panels, doped with different ratios of barite and boron carbide, were produced and characterized by optical and scanning electron microscopy (SEM). Gamma and neutron radiation shielding properties of these materials were investigated. The results have been compared with the lead as the standard shielding material.

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“…Thus, different shielding properties of building materials [1][2][3], ores [4], glasses [5,6], plastics and polymers [7], Lunar soil samples [8], gemstones, like the Amethyst [9], Boron containing materials [10], alloys [11], nanoparticles of W and polyethylene dispersed in polymer [12], and concrete with different aggregates [13][14][15][16] have been reported. Some of the shielding features include the effective atomic number, the effective electron density, the half value layer, the energy absorption and exposure buildup factors, the linear attenuation coefficient (P), and the mass attenuation coefficient (P U) for photons.…”

Section: Introductionmentioning

confidence: 99%

Photon Shielding Features of Quarry Tuff

et al. 2017

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Abstract. Cantera is a quarry tuff widely used in the building industry; in this work the shielding features of cantera were determined. The shielding characteristics were calculated using XCOM and MCNP5 codes for 0.03, 0.07, 0.1, 0.3, 0.662, 1, 2, and 3 MeV photons. With XCOM the mass interaction coefficients, and the total mass attenuation coefficients, were calculated. With the MCNP5 code a transmission experiment was modelled using a point-like source located 42 cm apart from a point-like detector. Between the source and the detector, cantera pieces with different thickness, ranging from 0 to 40 cm were included. The collided and uncollided photon fluence, the Kerma in air and the Ambient dose equivalent were estimated. With the uncollided fluence the linear attenuation coefficients were determined and compared with those calculated with XCOM. The linear attenuation coefficient for 0.662 MeV photons was compared with the coefficient measured with a NaI(Tl)-based J-ray spectrometer and a 137 Cs source.

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Comparative study of different concrete composition as gamma-ray shielding materials

Cited by 133 publications

References 13 publications

Neutron and photon scattering properties of high density concretes used in radiation therapy facilities: A Monte Carlo study

Neutron and photon scattering properties of high density concretes used in radiation therapy facilities: A Monte Carlo study

Production of Barite and Boroncarbide Doped Radiation Shielding Polymer Composite Panels

Photon Shielding Features of Quarry Tuff

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