Investigation on gamma-ray shielding and permeability of clay-steel slag mixture

Isfahani, Hajar Share; Abtahi, Sayyed Mahdi; Roshanzamir, Mohammad Ali; Shirani, Ahmad; Hejazi, Sayyed Mahdi

doi:10.1007/s10064-018-1391-6

Cited by 25 publications

(7 citation statements)

References 25 publications

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“…The average distance gamma rays traveled between two successive interactions at 1.41 MeV for the B-C1 sample is about 8.8 cm, while it is about 8 cm for the B-C3 sample. The present samples were compared with the similar previously studied shielded materials such nature bentonite samples [ 24 ], bentonite with steel slag [ 25 ], ordinary concrete and steel scrap [ 26 ] and ball and kaolin clays [ 27 ] at two different high energies, 1.173 and 1.332 MeV, and the results are listed in Table 4 .…”

Section: Resultsmentioning

confidence: 99%

Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability

et al. 2021

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The gamma-ray shielding ability of various Bentonite–Cement mixed materials from northeast Egypt have been examined by determining their theoretical and experimental mass attenuation coefficients, μm (cm2g−1), at photon energies of 59.6, 121.78, 344.28, 661.66, 964.13, 1173.23, 1332.5 and 1408.01 keV emitted from 241Am, 137Cs, 152Eu and 60Co point sources. The μm was theoretically calculated using the chemical compositions obtained by Energy Dispersive X-ray Analysis (EDX), while a NaI (Tl) scintillation detector was used to experimentally determine the μm (cm2g−1) of the mixed samples. The theoretical values are in acceptable agreement with the experimental calculations of the XCom software. The linear attenuation coefficient (μ), mean free path (MFP), half-value layer (HVL) and the exposure buildup factor (EBF) were also calculated by knowing the μm values of the examined samples. The gamma-radiation shielding ability of the selected Bentonite–Cement mixed samples have been studied against other puplished shielding materials. Knowledge of various factors such as thermo-chemical stability, availability and water holding capacity of the bentonite–cement mixed samples can be analyzed to determine the effectiveness of the materials to shield gamma rays.

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Section: Resultsmentioning

confidence: 99%

Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability

et al. 2021

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“…They found that for radiation shielding in the lower energy level of 660 keV, the use of clay with y ash up to 50% is recommended. Isfahani et al (2019) investigated the performance of clay used in low-level radioactive waste disposal centers by adding different percentages of steel slag, as a cheap and available industrial waste, to bentonite. They have examined two target parameters, namely hydraulic permeability and gamma-ray shielding.…”

Section: Introductionmentioning

confidence: 99%

Evaluating the performance of red mud and hematite powder additives of clay layer used in low-level radiation waste landfills

Salati

Isfahani

Rowshanzamir

et al. 2023

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Clay is used as the main material for the construction of landfill liners due to its unique properties such as low hydraulic permeability, self-healing performance, and availability. In addition to these properties, radiation shielding performance is a vital challenge for low-level radioactive waste disposal. In this study, the effect of two additives, including red mud and hematite are investigated on the radiation shielding and hydromechanical performance of bentonite clay. Experimental tests were performed on mixtures with 15, 30, and 45 percent of additives, and the shielding performance, hydraulic permeability, and mechanical strength have been investigated. Energy scattering (EDS) and scanning electron microscopy (SEM) tests have been performed to chemically analyze the mixture components and to define the linear attenuation coefficient by implementing simulation (MCNP code) and theoretical (XCOM database) methods. The results showed a good agreement between the experimental, simulation, and theoretical approaches. The best linear attenuation coefficient performance was reached by adding 15 percent of each additive while maintaining the hydraulic permeability and uniaxial strength in the acceptable range.

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“…In this study, the ANN method was used to develop a model by using our own experimental data that evaluates the concrete mixes' performance against radiation without compromising the mechanical properties of concrete. High radiation shielding ability could be achieved with the materials having relatively high density [56]. In the design of radiation shielding, thickness of the barrier or wall is an important parameter to be determined that attenuates the radiation to recommended values that depends on a material's properties.…”

Section: Introductionmentioning

confidence: 99%

Computational AI Models for Investigating the Radiation Shielding Potential of High-Density Concrete

et al. 2022

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Concrete is an economical and efficient material for attenuating radiation. The potential of concrete in attenuating radiation is attributed to its density, which in turn depends on the mix design of concrete. This paper presents the findings of a study conducted to evaluate the radiation attenuation with varying water-cement ratio (w/c), thickness, density, and compressive strength of concrete. Three different types of concrete, i.e., normal concrete, barite, and magnetite containing concrete, were prepared to investigate this study. The radiation attenuation was calculated by studying the dose absorbed by the concrete and the linear attenuation coefficient. Additionally, artificial neural network (ANN) and gene expression programming (GEP) models were developed for predicting the radiation shielding capacity of concrete. A correlation coefficient (R), mean absolute error (MAE), and root mean square error (RMSE) were calculated as 0.999, 1.474 mGy, 2.154 mGy and 0.994, 5.07 mGy, 5.772 mGy for the training and validation sets of the ANN model, respectively. Similarly, for the GEP model, these values were recorded as 0.981, 13.17 mGy, and 20.20 mGy for the training set, whereas the validation data yielded R = 0.985, MAE = 12.2 mGy, and RMSE = 14.96 mGy. The statistical evaluation reflects that the developed models manifested close agreement between experimental and predicted results. In comparison, the ANN model surpassed the accuracy of the GEP models, yielding the highest R and the lowest MAE and RMSE. The parametric and sensitivity analysis revealed the thickness and density of concrete as the most influential parameters in contributing towards radiation shielding. The mathematical equation derived from the GEP models signifies its importance such that the equation can be easily used for future prediction of radiation shielding of high-density concrete.

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Investigation on gamma-ray shielding and permeability of clay-steel slag mixture

Cited by 25 publications

References 25 publications

Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability

Enhancement of Bentonite Materials with Cement for Gamma-Ray Shielding Capability

Evaluating the performance of red mud and hematite powder additives of clay layer used in low-level radiation waste landfills

Computational AI Models for Investigating the Radiation Shielding Potential of High-Density Concrete

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