Investigation of gamma radiation shielding capability of two clay materials

Olukotun, S.F.; Gbenu, S.T.; Ibitoye, F.I.; Oladejo, O.F.; Shittu, H. O.; Fasasi, M.K.; Balogun, F.A.

doi:10.1016/j.net.2018.05.003

Cited by 106 publications

(28 citation statements)

References 16 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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“…Again, the attenuation efficiency of the composite is improved at high values of SR ð Þ. Olukotun et al [47] calculated the half-value layer (HVL) which is the necessary thickness for attenuation of 50% incident beam using Eq. 10.…”

Section: Theoretical Shielding Parameters In the Design Of Radiation Protective Materialsmentioning

confidence: 99%

Trends in reinforced composite design for ionizing radiation shielding applications: a review

2021

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This review explored recent developments in reinforced composite design and applications for improved radiation shielding and high percentage attenuation. Radiation energy moves as a wave. Thus unguarded exposure to high-energy radiation is inimical to the human tissue and the overall health standing of individuals which may result in cancer, tumour, skin burns and cardiovascular diseases. Radiation energy is conventionally contained using lead-based shields. However, recent literature has faulted the continued use of lead citing drawbacks such as high toxicity, poisoning, lack of chemical stability, heaviness and hazardous after life handling. Consequently, the trending research evidence has shown mass deviation towards the use of reinforced polymer composite as an alternative to lead due to their light weight, low cost, high resilience, good mechanical tenacity and interesting electrical properties. The present review therefore summarizes the criteria for ionizing radiation shielding material design, mechanism of radiation energy shielding, beam penetration in composite shielding materials, theoretical shielding parameters in the design of radiation protective materials, scheme of reinforced composite material selection for shielding purposes and various control variables in the design of composite for ionizing radiation shielding. In addition, an attempt was made to highlight gaps in research and draw future scope for further studies. It is expected that this review will give some guidance to the future exploration in the design and application of reinforced composite with respect to ionizing radiation shielding processes.

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“…Rare‐earth‐activated luminescent materials play a vital role in many fields of applied research such as in nuclear power plants, [ 1 ] radiotherapy, [ 2,3 ] personnel exposure, [ 4–6 ] and environmental release. [ 7 ] Rare‐earth impurities integrated into the host matrix may be a reason behind the changes in thermoluminescence (TL) properties with dosage.…”

Section: Introductionmentioning

confidence: 99%

Investigation of thermoluminescence response and trapping parameters of natural barite samples from Dongargaon mine, India

et al. 2020

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Dosimetry is a technique that quantitatively measures the ionizing radiation absorbed by matter. The present study was conducted on the barites from a mine at Dongargaon in Central India. Morphological and structural analysis of proposed sample was carried out using X‐ray diffraction and standard error of the mean. Thermal analysis and chemical composition of the proposed sample were carried out using thermogravimetric analysis and differential thermal analysis, and electron probe microanalysis. Thermoluminescence (TL) studies on a natural barite sample were performed using a Nucleonix TL1009I TL reader following sample irradiation with γ‐rays generated from a 60Co irradiation source. A broad TL glow curve was observed after TL study that was then deconvoluted using TLanal deconvolution software. Trapping parameters from the sample such as activation energy (E), order of kinetics (b), and frequency factor (s) were calculated using Chen’s peak shape method, the initial rise method, and Ilich’s method. The results indicated that the natural barite sample could be used in high‐dose TL dosimetric applications in various fields.

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Investigation of gamma radiation shielding capability of two clay materials

Cited by 106 publications

References 16 publications

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

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

Trends in reinforced composite design for ionizing radiation shielding applications: a review

Investigation of thermoluminescence response and trapping parameters of natural barite samples from Dongargaon mine, India

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