Gamma-ray attenuation coefficients of some building materials available in Egypt

Medhat, M.E.

doi:10.1016/j.anucene.2009.02.006

Cited by 88 publications

(32 citation statements)

References 11 publications

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“…Furthermore, we have observed that the linear attenuation coefficients of phantom materials decrease only slightly in the medium energy range (356.5, 661.6, 1173.2 and 1332.5 keV). This result agrees with the conclusions reported by Gurler and Akar Tarim [5] and Medhat [14]. Having observed this agreement, three other shielding parameters, namely the half-value layer, tenth-value layer, and mean free path, were also calculated using the simulation results.…”

Section: Discussionsupporting

confidence: 81%

“…The discrepancy in the values of the calculated and the measured coefficients could be due to deviations from narrow beam geometry in the source-detector arrangements, as suggested by Medhat [14] and Gurler and Akar Tarim [5].…”

Section: Resultsmentioning

confidence: 91%

“…The value of the linear attenuation coefficient depends on the incident photon energy, the atomic number, and the density of the absorber. Given that the linear attenuation coefficient depends on density ρ, it is expressed as a mass attenuation coefficient µ/ρ, representing the linear attenuation coefficient per unit mass density of the material [5,14]. Half-value layer (HVL), tenth-value layer (TVL), and mean free path (mfp) are the additional parameters that are calculated for gamma-ray shielding.…”

Section: Introductionmentioning

confidence: 99%

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Monte Carlo Calculations for Photon Attenuation Studies on Different Solid Phantom Materials

2017

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The linear attenuation coefficients of water and some solid phantom materials, namely of solid water RMI-457, of plastic water, of RW3 solid water, and of Perspex were determined by Monte Carlo calculations, for gammaray photons with energies of 59.5, 80.9, 140.5, 356.5, 661.6, 1173.2, and 1332.5 keV. The calculated values were compared with the experimental results presented by other researchers and with theoretical values obtained using the XCOM database. Good agreement was observed between the calculations, the experimental, and the theoretical values. The results indicate that the process in Monte Carlo code can be followed to determine the equivalency of other materials at several energies. Three shielding factors such as half-value layer, tenth-value layer, and mean free path were calculated at all considered gamma-ray energies.

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Section: Discussionsupporting

confidence: 81%

Section: Resultsmentioning

confidence: 91%

Section: Introductionmentioning

confidence: 99%

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Monte Carlo Calculations for Photon Attenuation Studies on Different Solid Phantom Materials

2017

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“…The scattering and absorption of gamma radiations are related to the effective atomic number of the materials 20 . These values are calculated using equation 3 and variation for the prepared samples is shown in figure 2.…”

Section: Effective Atomic Numbers and Half Value Layermentioning

confidence: 99%

Comparative Study of Radiation Shielding Parameters for Bismuth Borate Glasses

Kaundal

2016

Mat. Res.

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Melt and quench technique was used for the preparation of glassy samples of the composition x Bi 2 O 3 -(1-x) B 2 O 3 where x= .05 to .040. XCOM computer program is used for the evaluation of gamma-ray shielding parameters of the prepared glass samples. Further the values of mass attenuation coefficients, effective atomic number and half value layer for the glassy samples have been calculated in the energy range from 1KeV to 100GeV. Rigidity of the glass samples have been analyzed by molar volume of the prepared glass samples.

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“…The most important quantity characterizing the penetration and diffusion of gamma radiation in extended media is the attenuation coefficient, µ [7,[9][10][11][12][13]. This quantity depends on the photon energy E and on atomic number Z of the medium.…”

Section: Mass Attenuation Coefficientmentioning

confidence: 99%

Gamma Radiation Absorption Characteristics of Concrete with Components of Different Type Materials

et al. 2010

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Nuclear facilities as nuclear power stations, nuclear research reactors, particle accelerators and linear accelerator in medical institution using concrete in building construction. The different type materials of the aggregate as component of concrete were analyzed to provide radiation protection. The energy deposited the transmission factor and the mass attenuation coefficients in ordinary and barite concretes have been calculated with the photon transport Monte Carlo software. The numerical simulations results show that using barite as an aggregate in the concrete is one of the solutions for gamma ray shielding. Thereat, it is shown non-destructive method for determining the gamma radiation absorption characteristics of concrete.

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Gamma-ray attenuation coefficients of some building materials available in Egypt

Cited by 88 publications

References 11 publications

Monte Carlo Calculations for Photon Attenuation Studies on Different Solid Phantom Materials

Monte Carlo Calculations for Photon Attenuation Studies on Different Solid Phantom Materials

Comparative Study of Radiation Shielding Parameters for Bismuth Borate Glasses

Gamma Radiation Absorption Characteristics of Concrete with Components of Different Type Materials

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