Consistency and shielding efficiency of cement-bitumen composite for use as gamma-radiation shielding material

Saleh, Hosam M.; Bondouk, I.I.; Salama, E.; Esawii, Heba A.

doi:10.1016/j.pnucene.2021.103764

Cited by 47 publications

(22 citation statements)

References 26 publications

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“…Figure 1 illustrates bentonite, red, ball and kaolin clay samples labeled as A,B,C and D respectively. The porosity, P of the sample known as the ratio between the void volume and the total volume and can be calculated using the following equation [23,24].…”

Section: Methodsmentioning

confidence: 99%

Investigation of Photon Radiation Attenuation Capability of Different Clay Materials

et al. 2021

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This work aims to experimentally report the radiation attenuation factors for four different clays (red, ball, kaolin and bentonite clays) at four selected energies (emitted from Am-241, Cs-137, and Co-60). The highest relative difference in the mass attenuation coefficient (MAC) is equal to −3.02%, but most of the other results are much smaller than this value, proving that the experimental and theoretical data greatly agree with each other. From the MAC results, the shielding abilities of the clay samples at 0.060 MeV follow the order of: bentonite > red > ball > kaolin. Thus, at low energies, the bentonite clay sample provides the most effective attenuation capability out of the tested clays. The half value layer (HVL) increases as energy increases, which suggests that, only a thin clay sample is needed to sufficiently absorb the radiation at low energies, while at higher energies a thicker sample is needed to shield the same amount of high energy radiated. Furthermore, bentonite clay has the lowest HVL, while the kaolin clay has the greatest HVL at all energies. The radiation protection efficiency (RPE) values at 0.060 MeV are equal to 97.982%, 97.137%, 94.242%, and 93.583% for bentonite clay, red clay, ball clay, and kaolin clay, respectively. This reveals that at this energy, the four clay samples can absorb almost all of the incoming photons, but the bentonite clay has the greatest attenuation capability at this energy, while kaolin clay has the lowest.

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Section: Methodsmentioning

confidence: 99%

Investigation of Photon Radiation Attenuation Capability of Different Clay Materials

et al. 2021

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“…A study done on evaluating cement material in shielding from radioactive material emitting gamma rays, by mixing it with liquid bitumen to estimate their physical stability and isolation performance. Cement showed a high attenuation coefficient and isolation performance [ 14 ]. With the innovation of Monte Carlo simulations, shielding containers through aluminum, iron, copper, and lead were designed by irradiating a simulator of 137 Cs radioisotope to achieve the highest efficiency and light weight to be easily transported and stored.…”

Section: Introductionmentioning

confidence: 99%

Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study

ALMisned¹,

Baykal²,

Kılıç³

et al. 2023

Heliyon

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“…Due to the known toxic effects of lead and some problems arising from its weight, the search for new radiation shielding materials as an alternative to lead has gained momentum. Glasses [1][2][3], alloys [4][5][6], concretes [7][8][9], composites [10][11][12] and minerals [13,14] are included in the search new alternative products to lead. In addition to these, the choice of metallic glasses is a new alternative for use in this field, as their elements are adjustable up to a certain point.…”

Section: Introductionmentioning

confidence: 99%

Determination of Gamma Radiation Shielding Characteristics for Some Iron-Based Metallic Glasses

Akman

2023

Türk Doğa Ve Fen Dergisi

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In this study, the gamma radiation shielding characteristics of metallic glasses having Fe81B13.5Si3.5C2, Fe79B16Si5, Fe78B13Si9 and Fe40Ni38B18Mo4 components and coded as FeBSiC, FeBSi1, FeBSi2 and FeNiBMo were investigated. In order to investigate, the mass attenuation coefficients for metallic glasses in the photon energies range of 0.060 to 2.614 MeV were calculated with the help of WinXCOM program and GEANT4 and FLUKA simulation codes. The linear attenuation coefficient, half and tenth value layers, mean free path, effective atomic number and electron density parameters were calculated with the help of the calculated mass attenuation coefficients. Variations of the calculated gamma radiation shielding parameters with photon energy were discussed. It was observed that mass and linear attenuation coefficients, effective atomic number and electron density parameters decreased with increasing photon energy, while half and tenth value layers and mean free path parameters increased with increasing photon energy. It has been observed that metallic glasses have better gamma shielding capabilities in the low photon energy region, and metallic glass coded as FeNiBMo has better gamma radiation shielding capacity than other studied metallic glasses.

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Consistency and shielding efficiency of cement-bitumen composite for use as gamma-radiation shielding material

Cited by 47 publications

References 26 publications

Investigation of Photon Radiation Attenuation Capability of Different Clay Materials

Investigation of Photon Radiation Attenuation Capability of Different Clay Materials

Comparative analysis on application conditions of indium (III) oxide-reinforced glasses in nuclear waste management and source transportation: A Monte Carlo simulation study

Determination of Gamma Radiation Shielding Characteristics for Some Iron-Based Metallic Glasses

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