The effect of boron waste on the radiation shielding properties of cement

Korkmaz, Abdul Vahap; Can, Ömer; Kayiran, Hüseyin Fırat

doi:10.1007/s12517-021-09364-6

Cited by 6 publications

(2 citation statements)

References 52 publications

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“…σ a is calculated using Eq. ( 7 ) 53 and provides the probability of interaction per atom within the material’s unit volume. where N is Avogadro’s number, A i and f i are the atomic weight and fractional weight for each target element, respectively.…”

Section: Methodsmentioning

confidence: 99%

Attenuation properties of poly methyl methacrylate reinforced with micro/nano ZrO2 as gamma-ray shields

Alabsy,

Abbas,

El-khatib

et al. 2024

Sci Rep

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This research aimed to examine the radiation shielding properties of unique polymer composites for medical and non-medical applications. For this purpose, polymer composites, based on poly methyl methacrylate (PMMA) as a matrix, were prepared and reinforced with micro- and nanoparticles of ZrO2 fillers at a loading of 15%, 30%, and 45% by weight. Using the high purity germanium (HPGe) detector, the suggested polymer composites’ shielding characteristics were assessed for various radioactive sources. The experimental values of the mass attenuation coefficients (MAC) of the produced composites agreed closely with those obtained theoretically from the XCOM database. Different shielding parameters were estimated at a broad range of photon energies, including the linear attenuation coefficient (μ), tenth value layer (TVL), half value layer (HVL), mean free path (MFP), effective electron density (Neff), effective atomic number (Zeff), and equivalent atomic number (Zeq), as well as exposure buildup factor (EBF) and energy absorption buildup factor (EABF) to provide more shielding information about the penetration of γ-rays into the chosen composites. The results showed that increasing the content of micro and nano ZrO2 particles in the PMMA matrix increases μ values and decreases HVL, TVL, and MFP values. P-45nZ sample with 45 wt% of ZrO2 nanoparticles had the highest μ values, which varied between 2.6546 and 0.0991 cm−1 as γ-ray photon energy increased from 0.0595 to 1.408 MeV, respectively. Furthermore, the highest relative increase rate in μ values between nano and micro composites was 17.84%, achieved for the P-45nZ sample at 59.53 keV. These findings demonstrated that ZrO2 nanoparticles shield radiation more effectively than micro ZrO2 even at the same photon energy and filler wt%. Thus, the proposed nano ZrO2/PMMA composites can be used as effective shielding materials to lessen the transmitted radiation dose in radiation facilities.

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Section: Methodsmentioning

confidence: 99%

Attenuation properties of poly methyl methacrylate reinforced with micro/nano ZrO2 as gamma-ray shields

Alabsy,

Abbas,

El-khatib

et al. 2024

Sci Rep

View full text Add to dashboard Cite

show abstract

“…They measured dose rate, mean free path, and total neutron cross-section for the three materials. they concluded that, the boron is the best neutron shielding material in comparison with the others [22] investigated waste boron's impact on radiationshielding qualities. Three different densities of cement have been used according to the percentage of boron waste added to the cement (Cement's density was reduced by boron waste addition).…”

Section: This Study Aims To Review the Efficiency Of Different Filler...mentioning

confidence: 99%

Radiation Shielding Against Neutron Using Different Fillers: Review Study

Mohamedy¹

2023

Arab Journal of Nuclear Sciences and Applications

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Radiation Shielding Concrete is mixture of cement, water, and heavy weight Aggregates (Fillers) commonly used as shielding against radiation as neutrons that emitted in different facilities as the medical units, particle accelerators. Neutrons causing extra doses to the patient and the occupational workers which is the main issue to grantee radiation safety. Various special Concretes containing fillers have been produced and used for enhancing the radiation shielding characteristics of the ordinary concrete. Only light elements as boron and hydrogen acts as moderate for neutrons that can absorb them. Therefore, for neutrons radiation shielding; concrete must contain light elements beside the heavy elements. Many softwires were employed to examine the effectiveness of the concretes as a radiation shielding materials, also Monte Carlo (MC) simulation program that simulates the transmission and interaction of radiation with different matters. Those software and simulation programs can be used in different fields such as, radiation physics, medicine, and researches. In this paper different fillers added to the ordinary concrete and different measuring methods will be reviewed.

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Radiation shielding and experimental characteristics of tincal waste added with obsidians

Aygun,

Astam,

Aygun

2024

Int. J. Environ. Sci. Technol.

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The use of natural resources and waste products represents an effective way of addressing a pressing concern for the future of the global population. It is therefore crucial to evaluate wastes and natural materials as raw materials in many industries. The present study sought to investigate the radiation protection features and experimental characteristics of tincal waste added with obsidians from Eastern Turkey (Nemrut, Pasinler, Sarıkamış and Ikizdere regions). Fourier transform infrared spectrometry, X-ray diffraction, Scanning electron microscopy and Energy dispersive spectroscopy were used to have knowledge for morphological and structural properties of the samples. The X-ray diffraction analysis of the samples with higher obsidian content revealed an amorphous structure with a minor presence of crystalline phases. In contrast, the samples with a higher tincal waste content exhibited crystalline phases. Based on morphologic results, it can be said that obsidian samples exhibited relatively smooth and glassy surfaces, whereas tincal waste displayed a rough surface comprising randomly shaped small particles. In addition, radiation attenuating abilities of the tincal waste added with obsidians were determined by the calculation of tenth value layers, half value layers, mean free paths, mass attenuation coefficients, linear attenuation coefficients, fast neutron removal cross sections, effective atomic numbers and buildup factors using the newly produced Phy-X/PSD code. It is obtained that the samples show good radiation protection performances and the samples can be evaluated as better radiation shields for radiation applications especially in construction industry.

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The effect of boron waste on the radiation shielding properties of cement

Cited by 6 publications

References 52 publications

Attenuation properties of poly methyl methacrylate reinforced with micro/nano ZrO2 as gamma-ray shields

Attenuation properties of poly methyl methacrylate reinforced with micro/nano ZrO2 as gamma-ray shields

Radiation Shielding Against Neutron Using Different Fillers: Review Study

Radiation shielding and experimental characteristics of tincal waste added with obsidians

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