Mass Attenuation Coefficients Research Articles

SrO–ZnO–PbO–B2O3 glassy insights: Unveiling the structural and optical features for gamma ray shielding efficacy

The melt-quenching approach was utilised to synthesize amorphous SrO–ZnO–PbO–B2O3 glasses, with FTIR spectroscopy applied to the samples to reveal the various bonds' stretching and bending vibrations. With PbO introduced to the network, the UV–Vis absorption spectrum's absorption peak shifts towards the higher wavelength values, while Tauc plot analysis of the UV–Vis spectra reveals a 2.957–2.569 eV decrease in the band gap energy. The radiation shielding properties are examined via Phy-X program. The mass attenuation coefficient (MAC) has an inverse relation with the energy, which demonstrated the greater penetration ability of radiation that contains higher energy. In terms of the MAC values at low energies the results revealed a greater difference, while they are almost identical at higher energies. The linear attenuation coefficient (LAC) was evaluated and the chemical composition's influence discussed, with the LAC values in the order of SZPB1 <SZPB2 <SZPB3 <SZPB4. This confirms that the PbO addition leads to increased LAC values. The half value layer (HVL) decreases with increased concentration of PbO. This suggests that the higher the glass system's PbO content, the thinner the glass system needs to be to attenuate half of the incoming photons.

Assessment of radiation shielding capability of a high-density TeO2–Tl2O–Ag2O glass system: A simulation and theoretical studies

We investigated the shielding properties of four selected glass samples among the 66 samples. These glass samples had the following compositions and densities: S1 (55TeO2+45Ag2O, density 6.28 g/cm3), S2 (55TeO2+5Tl2O+40Ag2O, density 6.37 g/cm3), S3 (50TeO2+15Tl2O+35Ag2O, density 6.49 g/cm3), and S4 (40TeO2+55Tl2O+35Ag2O, density 7.20 g/cm3). These glasses exhibit high density. We compute the mass attenuation and linear attenuation coefficients for these samples using MCNPX simulations and Phy-X software between 0.001 MeV and 15 MeV energy range. The derived mass attenuation coefficient (MAC) enables the calculation of key radiation shielding metrics. The tenth value layer, the half value layer (HVL), the mean free path (MFP), and the effective atomic number (Zeff) were also determined. Values of LAC values for S1, S2, S3 and S4 glasses span 244.91 to 0.24932 cm⁻1, 319.52 to 0.2625 cm⁻1, 447.24 to 0.28491 cm⁻1 and 379.480 to 0.273 cm−1, respectively. Correspondingly, HVL values range from 0.0028 to 2.78005 cm, 0.0021–2.6403 cm, and 0.00154–2.4327 cm and 0.002135–2.917403 cm for S1, S2, S3 and S4 glasses, respectively. Our findings reveal that results from both MCNPX and Phy-X exhibit consistency, supported by computed relative differences. Notably, the glass sample with a relatively higher TlO2 concentration demonstrates superior shielding properties across the entire energy spectrum. Importantly, these glass samples can significantly lower the strength of the x-rays and γ-rays.

Synthesis and Gamma-ray Shielding Efficiency of Borosilicate Glasses Doped with Zinc Oxide: Comparative Study

AbstractThis study examined the suitability of several glass compositions as a gamma-ray shielding substance. The compositions tested were of varying ZnO concentrations, specifically (60-x) B2O3—10Na2O—15SiO2—5Al2O3—(x + 10)ZnO (where X = 5, 10, 15 and 20 mol%). Measurements were performed at energy levels of 0.6642, 1.1776, and 1.3343 MeV radiated from Cs137 and Co60 point sources along with a scintillation detector [NaI(TL)]. We investigated the critical properties related to gamma radiation shielding, determining the effective atomic number (Zeff), electron density (Nel), half-value layer (HVL), linear attenuation (μ) and mass attenuation (μm) coefficients, and mean free path (λ). Our results show that the glasses under examination get denser (from 2.12 to 2.77 g/cm3) as the Zn concentration rises from 15 to 35 mol %. In addition, all glass compositions provide adequate protection against gamma radiation at the specified energy levels. The values of µ went up from 0.157 to 0.214 cm−1 (0.6642 MeV), from 0.119 to 0.160 cm−1 (1.1776 MeV), and from 0.114 to 0.151 (1.3343 MeV). For samples B1 and B4, the observed HVL values dropped from 4.41, 5.84, and 6.12 cm to 3.21, 4.31, and 4.61 cm at 0.6642, 1.1736, and 1.3343 MeV, respectively. Among the materials tested, prepared glasses show higher shielding capacity compared to regularly used glass and concrete samples. The study highlights these glass compositions' potential as practical materials that can shield gamma radiation.

Polyurethane reinforced with micro/nano waste slag as a shielding panel for photons (experimental and theoretical study)

This study not only provides an innovative technique for producing rigid polyurethane foam (RPUF) composites, but it also offers a way to reuse metallurgical solid waste. Rigid polyurethane (RPUF) composite samples have been prepared with different proportions of iron slag as additives, with a range of 0–25% mass by weight. The process of grinding iron slag microparticles into iron slag nanoparticles powder was accomplished with the use of a high-energy ball mill. The synthesized samples have been characterized using Fourier Transform Infrared Spectroscopy, and Scanning Electron Microscope. Then, their radiation shielding properties were measured by using A hyper-pure germanium detector using point sources 241Am, 133 BA, 152 EU, 137Cs, and 60Co, with an energy range of 0.059–1.408 MeV. Then using Fluka simulation code to validate the results in the energy range of photon energies of 0.0001–100 MeV. The linear attenuation coefficient, mass attenuation coefficient, mean free path, half-value layer and tenth-value layer, were calculated to determine the radiation shielding characteristics of the composite samples. The calculated values are in good agreement with the calculated values. The results of this study showed that the gamma-ray and neutron attenuation parameters of the studied polyurethane composite samples have improved. Moreover, the effect of iron slag not only increases the gamma-ray attenuation shielding properties but also enhances compressive strength and the thermal stability. Which encourages us to use polyurethane iron-slag composite foam in sandwich panel manufacturing as walls to provide protection from radiation and also heat insulation.

Efficacy of Ni2+ on modification the structure, ultrasonic, optical, and radiation shielding behaviors of potassium lead borate glasses

This paper presents the method of preparing (60 − x) B2O3–20 K2O–20 PbO–x NiO, coded as (NiO x), and x = (0–10 mol%) glass systems fabricated through the melt-quench technique. The prepared glass was characterized through X-ray diffraction spectra (XRD); the mechanical behavior of the glass samples was investigated using the ultrasonic technique, Fourier transform infrared (FTIR) spectra, the optical reflectance R(λ), refractive index (n), optical conductivity (σopt), the dispersion parameters of the studied samples were deduced using Wemple and Di-Domenico models. The results obtained were reported in detail. One of the fundamental parameters used to evaluate the interaction of radiation with shielding material was the mass attenuation coefficient (μm), which was obtained using Phy/X software and PHITS code program. It was used to calculate radiation interaction parameters, e.g., linear (μL) attenuation coefficient, effective atomic number (Zeff), half value layer HVL, mean free path (MFP) and the average atomic cross section, σt. Comparing the shielding behavior of the glass samples revealed that (NiO 10) glass demonstrated the highest μm and μL compared to the other samples. The maximum μm values equal 48.13, 48.73, 49.42, 50.59, and 51.08 cm2/g for (NiO 0) to (NiO 10), recorded at 0.015 MeV, respectively. This study shows that increasing the amount of NiO in the preferred glass samples leads to achieving high-performance radiation shielding materials.Graphical abstract

An experimental and theoretical study to evaluate Al2O3–PbO–B2O3–SiO2–BaO radiation shielding properties

This study's objective is to evaluate an Al2O3–PbO–B2O3–SiO2–BaO glass system's radiation shielding characteristics. The composition of the glasses is 15Al2O3–25PbO–(60-x)B2O3–10SiO2–xBaO, with x in the 5–20 mol% range. Experimental results were used to determine the samples' linear attenuation coefficients (LAC), which were then confirmed by Phy-X program. Utilizing narrow beam transmission geometry, the experimental LAC values were determined. According to the results there was high agreement when comparing the theoretical and experimental values. The LAC values were used to calculate the prepared glasses' mass attenuation coefficients (MAC) and other relevant properties. The mean free path (MFP) values of the sample with 5 mol% BaO were 0.079, 2.549, 3.944 and 4.273 cm at 0.0595, 0.662, 1.173, and 1.332 MeV, thus demonstrating that raising the glass system's BaO enhances the prepared glasses' shielding capacity. According to radiation protection efficiency (RPE), the glasses' capacity to shield the photon is enhanced when their BaO content rises.

Radiation attenuation properties of transparent aluminum oxynitride: a comprehensive study

The investigation of radiation-durable materials with outstanding gamma shielding capabilities and lead-free alternatives remains a compelling area of research. This study fills a critical gap by exploring, for the first time, the radiation attenuation properties of the novel material aluminum oxynitride (AlON) and its shielding mechanism. Utilizing the XCOM database and Geant4 Monte Carlo simulation toolkit, we systematically examined AlON’s linear attenuation coefficient, mass attenuation coefficient, half-value layer, tenth-value layer, mean-free path, effective atomic number, and effective electron density. Comparing AlON to traditional shielding materials and glasses, including both lead-containing and lead-free compositions, our study suggests its superiority over concrete and lead-free glasses. At higher energies, AlON demonstrates comparability with lead-doped materials. These findings contribute valuable insights into the potential applications of AlON across diverse radiation shielding contexts. This research provides a foundational understanding of AlON’s radiation attenuation capabilities, paving the way for future exploration and practical applications in the field of gamma shielding.

Investigation the Gamma Ray Shielding Parameters for Portland Cement Doped with Several Metal Oxides

In this research, gamma ray photons emitted from radioactive sources (Cs-137, Ra-226) with energies (186, 242, 295, 352, 609, 662, 1120, 1765) keV, respectively, to study some parameters, Such as the linear attenuation coefficient ( , mass attenuation coefficient ( for shield made of composite materials consisting of cement as the base material reinforced with different materials (magnesium oxide MgO , tungsten oxide WO3) nanoparticles with different reinforcement ratios (10, 30, 50) % and thickness (0.5) cm to protect against radiation. For this purpose, a sodium iodide detector activated with thallium with dimensions ( was used with an integrated measuring system, to determine the suitability of these shields for use in the field of gamma ray protection. The results showed that the values ​​of these parameters are affected by changing the reinforcement ratios and the gamma ray energy. It was found that when increasing the reinforcement ratio of the shield led to an increase in the linear and mass attenuation coefficient, and in contrast, a decrease in the values ​​of each occurs when the gamma ray energy of the used radioactive source is increased, especially at a concentration of 50 % and at energy (1765) Kev.

Characterization and radiation shielding efficiency of MWCNT/shape memory ternary blend composite films

In this study, the structural, X-ray and gamma-ray, and neutron shielding properties of shape memory ternary blend/multi-walled carbon nanotube (MWCNT) composite films were investigated. The composition of the composite films was defined as (100-x) poly (ε-caprolactone) (PCL):polyethylene glycol (PEG):polyvinyl chloride (PVC) + xMWCNT, where x = 0, 1, 3, 5% (mole percentage). The ternary blend/MWCNT composite films were characterized using Attenuated Total Reflectance Infrared Spectroscopy (ATR-IR), Thermogravimetric Analysis (TGA), Differential Scanning Calorimetry (DSC), X-ray Diffraction (XRD), and Scanning Electron Microscopy (SEM). Thermal results showed that the degradation temperatures of composite materials with two degradation curves increased with increasing MWCNT percentage. The appearance of the MWCNT signal along with the characteristic polymer signals in the XRD pattern may be evidence that MWCNT is homogeneously distributed in the polymer blend. The mass attenuation coefficients (MAC), half-value layer (HVL), mean free path (MFP), and effective atomic numbers (Z_eff) of the composite films were experimentally measured over an energy range of 8.04–383.85 keV. Additionally, the equivalent dose rates for fast neutrons were measured, and the exposure buildup factor (EBF) and fast neutron removal cross-section (Σ_R) were theoretically calculated. The proton and alpha shielding parameters of the ternary blend/MWCNT composite films were determined, revealing that the inclusion of higher amounts of MWCNTs in the composite structure significantly improved capability of the films in shielding against radiation and neutrons.

Impact of Bi2O3 on the glass system B2O3 -TeO2–MgO–PbO on the purpose of radiation shielding efficacy

In this study, eight glass samples were prepared with the composition of [x Bi2O3-(75-x) B2O3–15TeO2 –5MgO–5PbO; where x = 0, 10, 20, 25, 30, 40, 50, and 60 mol%]. In the composition of those glass samples, various amountsof B2O3 were replaced by Bi2O3 to improve the glass material's radiation shielding capability. The mechanical properties of these glasses have been evaluated using densimeter and microhardness. The Vickers microhardness (Hv) slightly decreases as the amount of Bi2O3 increases due to the formation of Non-Bridging Oxygen (NBO). To evaluate the radiation shielding effectiveness of the prepared glass samples, we performed Monte Carlo simulations of several shielding parameters. The mass attenuation coefficients of the experimentally produced BTMPBi glass series were calculated using NIST and MCNP6, and reasonable agreement was found between the simulation and experimental results. The relative difference between NIST and MCNP6-based results was calculated, and the maximum deviation was 2.21% for the 1173 keV gamma ray incident in the BTMPBi60 glass sample. The value of the mean free path of those prepared glass samples maintained the following trend - BTMPBi0> BTMPBi10> BTMPBi20> BTMPBi25> BTMPBi30> BTMPBi40> BTMPBi50>BTMPBi60. The prepared glass sample BTMPBi0 showed a 2.6 times higher value of the mean free path at energy 1332 KeV compared with the prepared BTMPBi60. Analyzing the composition of the prepared glass samples, it is clear that the greater the amount of Bi2O3 the greater the value of linear attenuation coefficient (LAC) and effective atomic number. Based on the results, it can be concluded that the glass sample containing 60 mol % of Bi2O3 (BTMPBi60) exhibited the highest radiation shielding capability among all of the prepared samples.

Investigate various shielding parameters for (C18H20O8)x (ZrSiO4)100-x and (C18H20O8)x (BiClO)100-x in medical radiological applications

This study investigates some of shielding parameters of (C18H20O8)x (ZrSiO4)100-x and (C18H20O8)x (BiClO)100-x, x=(95,80,65,50)% wt coded as (S1,S2) for medical radiation application. We employed a theoretical model to calculate a mixture’s mass attenuation coefficients (MAC) during our investigation. The XCOM computer program was utilized for this purpose within the energy range of (0.356,0.364,0.44,0.662,0.739,0.834,0.846,1.17,1.238,1.274,1.33,1.368 and 2.754) MeV. The MAC values were used to compute several parameters, such as the linear attenuation coefficient LAC, half-value layer HVL, and effective atomic number Z eff . The study’s findings revealed a consistent decrease in the value of LAC as the energy increased for all the mixtures. The maximum value of LAC is 0.366 cm−1 in energy 0.356 MeV at x=50 for S2. The results show that adding BiClO to a matrix material can greatly improve its attenuation properties and be used to protect against medical radiation. The results show that the values of Z eff decreased with increasing energies, then stabilized and changed slightly at increasing energy. The lowest HVL values and the best for shielding were in group S2. The investigation also examined the association between the Z eff and the LAC at the value of x=50. The results show the correlation was positive and strong.

Radiation shielding properties of composites of TiZrNbHfTa refractory high entropy alloy reinforced with TiZrNbHfTaOx high-entropy oxide

Radiation shielding materials play a critical role in advancing the next generation of nuclear reactors. Among these, high-entropy materials with refractory properties emerge as a new category for radiation shielding applications. This study introduces TiZrNbHfTa-TiZrNbHfTaOx composites tailored for such purposes. Initially, a TiZrNbHfTa refractory high-entropy alloy (RHEA) is synthesized via mechanical alloying, followed by the oxidation of the alloy to obtain its refractory high-entropy oxide (RHEO), TiZrNbHfTaOx. Composites are then prepared by blending 5%, 10%, and 20% weight fractions of RHEO with RHEA using mechanical alloying. Comparative analysis of shielding properties reveals a decrease in mass attenuation coefficient and effective atomic number with increasing RHEO content. While RHEA exhibits superior shielding performance against gamma photons and neutrons, the composite containing 20% RHEO emerges as the optimal shield against alpha and proton irradiations. The equivalent neutron dose rate and removal cross-section values are obtained 49.8% and 0.142 for the composite with 20% RHEO, respectively. These findings, supported by computational simulations in this study, contribute valuable insights for the advancement of novel shielding materials crucial for future nuclear reactor technologies.

Attenuation coefficient for Agarwood and shade tree sections at 59.6keV and 356keV

Attenuation coefficient for Agarwood and shade tree sections at 59.6keV and 356keV

A comprehensive study of the shielding ability from ionizing radiation of different mortars using iron filings and bismuth oxide

The current work discusses the radiation attenuation capability and different shielding characteristics of different mortar samples. The samples were prepared by replacing different percentages of fine aggregate with iron filling and replacing different percentages of hydrated lime with Bi2O3 (0–50 wt.%). The prepared mortar samples are coded as CHBFX where X = 0, 10, 30, and 50 wt.%. The mass and linear attenuation coefficient was determined experimentally using a narrow beam technique, where a high purity germanium detector, and different point gamma-ray sources (such as Am-241, Cs-137, and Co-60). The linear attenuation coefficient was also calculated using the Monte-Carlo simulation code and the online Phy-X/PSD software. The comparison of the three methods showed a good agreement in the results. The linear attenuation coefficient drops from 19.821 to 0.053 cm−1 for CHBF0, from 27.496 to 0.057 cm−1 for CHBF10, from 42.351 to 0.064 cm−1 for CHBF30, and from 55.068 to 0.071 cm−1 for CHBF50 at photon energy range from 0.015 to 15 MeV. The half-value layer thickness, tenth-value layer thickness, and mean free path of the prepared mortar composites were also calculated photon energy ranged from 0.015 to 15 MeV. The fast neutron removal cross-section of the prepared CHBFX mortar samples have values of 0.096 cm−1, 0.098 cm−1, 0.103 cm−1, and 0.107 cm−1 for the mortar samples CHBF0, CHBF10, CHBF30, and CHBF50, respectively. The results showed that the mortar sample with the highest iron filing concentration, CHBF50, provides the best protection against gamma rays and fast neutrons which could be used in the nuclear and medical fields.

Impact of neodymium oxide (Nd2O3) substitution in barium–boron-phosphate glasses: A pathway to superior mechanical, optical, and radiation shielding performance

This study delves into the impact of substituting Nd2O3 for Na2O in Barium–Boron-Phosphate glasses, aiming to enhance their mechanical strength, optical characteristics, and radiation shielding efficacy. Glasses with a composition of 50B2O3 + 20P2O5 + 20BaO + (10-x)Na2O + xNd2O3 (x = 0, 1, 2, 3, 4 mol%) were synthesized and characterized. The findings indicate that as the Nd/Na ratio increases, the density of the glass also rises within the range of 3.77–4.23 g/cm3. Moreover, the addition of Nd leads to notable alterations in the optical characteristics of the resulting glasses. Specifically, there is a shift observed in the UV absorption edges, coupled with a noticeable increase in absorption at visible wavelengths. Moreover, Nd2O3 addition reduced the Urbach energy (from 0.6018 to 0.2239 eV for Nd0-Nd4) and the optical band gap indicating improved electronic structure and decreased disorder. The mechanical properties studied using the Makishima-Mackenzie model show As the replacement ratio of Nd2O3 increases, there is a noticeable improvement in the glass's mechanical robustness. Importantly, Glasses with high Nd/Na ratio in their composition exhibit enhanced radiation shielding capabilities, evidenced by increased mass attenuation coefficients and effective removal cross-sections for photons and fast neutrons, respectively. These findings suggest that Nd2O3-doped glasses offer a promising pathway for developing superior radiation shielding materials with tailored properties for diverse applications in nuclear facilities, medical devices, and space exploration equipment.

Radiation and nuclear shielding performance of tellurite glass system containing Li2O and MoO3: XCOM and FLUKA Monte Carlo

This study investigates the radiation attenuation properties of tellurite-based glasses with the chemical formula 75TeO2-(24-x)Li2O-(x)MoO3–1V2O5 (TLMV), where x = 0, 12, 24 mol%. The research focuses on important radiation protection values, such as the linear attenuation coefficient (μ), mass attenuation coefficient (μ/ρ), effective atomic number (Zeff), effective electron density (Neff), mass energy-absorption coefficient (MEAC), specific gamma-ray constants (Γ), gamma dose rate (Dr), mean free path (λ), half value layer (d1/2), and removal of fast neutrons (∑R). The gathered results indicate that changing Li2O and MoO3 mol% concentrations significantly impact shielding effectiveness. Additionally, this study compares the radiation shielding of TLMV glasses with commercial glasses, providing a comprehensive analysis for applications in healthcare, industrial, and related fields and exploring the potential usage of TLMV glasses in various shielding scenarios.

Computational Codes for Fast Neutrons and Gamma Ray Interactions Coefficients in Different Material

In this research, many materials used as shields against ionizing radiation (neutrons and gamma rays) were studied. Seven glass systems compounds and five polymeric compounds were used to test their effectiveness in attenuating fast neutrons. These compounds are (S1-S7) as shown in table (1) and polymeric compounds as shown in table (3), many attenuation coefficients for these compounds were calculated through the use of a computer program called (SAZ) written in the Python programming language, which is used to calculate a number of basic parameters based on certain semi-empirical equations. The results showed that the sample (S7) and C9H9O is the best glass system compound and polymeric compound for neutrons attenuation, because they have a largest value of ΣR. Also, a number of Eco-friendly metallic compounds as shown in table (2) were used, to test them in shielding against gamma rays. The mass attenuation coefficient was calculated through the NIST-XCOM program for a range of energies starting from 59.53 keV up to 1 GeV. These compounds differed in their ability to attenuate gamma rays, as the results showed that the best studied compound against gamma rays was the PbS compound because it contains the Lead element, which has a largest atomic number.

Synthesis and characterization of FMWCNTs/ZnO doped PVDF nanocomposites for enhanced mechanical, dielectric, and radiation shielding properties

This study investigates the enhancement of radiation shielding properties of polyvinylidene fluoride (PVDF) through the incorporation of functionalized multi-walled carbon nanotubes (FMWCNTs) and zinc oxide nanoparticles (ZnONPs), aiming to develop a lightweight, effective, and environmentally friendly shielding material. PVDF-based nanocomposites with varying concentrations of FMWCNTs@ZnO (0.0, 0.5, 1.0, 1.5, and 3.0 wt%) were synthesized using a solution casting method. Morphological analysis via high-resolution transmission electron microscopy (HRTEM) and field emission scanning electron microscopy (FESEM) confirmed the uniform dispersion of FMWCNTs@ZnO within the PVDF matrix. X-ray diffraction (XRD) studies revealed an increase in the β-phase crystallinity of PVDF at 1 wt% FMWCNTs@ZnO concentration, with a notable peak shift indicating enhanced polar group development. Vickers microhardness tests showed a significant improvement, with hardness values increasing from 342.5 kg/mm2 for pure PVDF to 391.2 kg/mm2 for nanocomposites containing 3 % FMWCNTs@ZnO. Dielectric analyses demonstrated increased permittivity and a dynamic relaxation behavior indicative of improved charge carrier density and interfacial polarization. Gamma shielding efficiency, assessed through linear attenuation coefficients (GLAC) and mass attenuation coefficients (GMAC), exhibited superior performance at lower photon energies (80 keV), with the highest GLAC and GMAC values observed for the 3 wt% FMWCNTs@ZnO doped samples. These findings underscore the potential of FMWCNTs@ZnO doped PVDF nanocomposites as promising materials for radiation shielding applications, offering a synergistic approach to enhancing mechanical, dielectric, and protective properties against ionizing radiation.

Radiation attenuation characterization of some biological samples by using the Klein–Nishina formula

Radiation has beneficial applications in medicine and nuclear sciences, but it can also be harmful due to its ionizing properties. So, radiation usage has a significant role in different research fields. In the present study, the Klein–Nishina (K–N) approach was used to evaluate the electronic and energy-transfer cross sections of Water, bone, adipose, soft, long, breast, brain and skin tissues. Compton mass attenuation coefficients (CMAC) and Compton mass energy transfer coefficients (CMACtr) were determined in the energy range 0.284–15 MeV. Different methods, based on the effective charge, were used to determine the parameters of the materials for the energy range. The cross sections were firstly calculated for elements that made up the materials. The investigated parameters of the materials were then determined using the relevant cross sections in the energy range. The results were compared with each other and some possible results from the literature. Klein–Nishina electronic cross sections, Compton mass attenuation coefficients and Compton mass energy transfer coefficients of the studied materials were decreased with increasing γ-ray energy like the elements. A good agreement was observed for CMACs and CMACtrs based on Zeff1/A and Zeff3/A (Diff. ≤ 16.4%) for Bone Compact. In addition, a comparison with the literature was done for CaCO3 in CMAC for some photon energies. The maximum difference (%) between used methods and literature was observed as ≤ 19.0%. The reported data should be useful using the gamma rays in Compton scattering energy region.

Investigation of natural radionuclides and radiation shielding potential of some commonly used building materials in Northwestern Nigeria

This study assessed the gamma-ray shielding potential of clay, sand, gypsum and kaolin commonly used as a building material in Northwestern, Nigeria. The radiological status of the samples was first evaluated by determining the activity concentrations of 238U, 232Th and 40K using NaI (Tl) detector after which elemental composition and mass density were determined using Neutron Activation Analytical Technique. After which the mass attenuation coefficients (MAC), linear attenuation coefficients (LAC), half value layer (HVL), tenth value layer (TVL), and effective atomic number (Zeff) were determined experimentally and theoretically using standard point sources of 137Cs and 60Co photon peaks (0.662 and 1.332, 1.173) MeV and Py-MLBUF software. The activity concentrations were found to range from 51 to 59 Bq kg−1 with a mean value of 59 Bq kg−1 for 238U, 24 to 27 Bq kg−1 with a mean value of 29 Bq kg−1 for 232Th, and 219 to 247 Bq kg−1 with a mean value of 247 Bq kg−1 for 40K which were about within the world recommended values of 33, 45 and 420 Bq kg−1 respectively. The results of the elemental compositions show that Si, Al, K, Fe, and Ba in clay and sand samples have concentrations in the range of 36.83–78.48%, 1.92–26.05%, 6.33–21.96%, 2.39–19.09%, and 0.09–1.44%, respectively, while in kaolin and gypsum, results revealed that Si, Al, K, Fe, and Ca range between 0.34 and 65.52%, 1.14–35.82%, 0.00–12.12%, 0.00–5.77%, and 0.00–96.6%, respectively. However, the concentrations of other elements such as Mg, Ti, Mn, Zn, Na, and Ba varied significantly with the samples. The results showed that clay has an average density of 1.96 g/cm3, sand has 2.32 g/cm3, kaolin has 2.63 g/cm3, and gypsum has the highest density with a value of 2.66 g/cm3 compared to other samples. During the measurements, a thallium-activated sodium-iodide NaI (TI) detector was used. A narrow beam transmission geometry condition was adopted for the measurements to ensure minimal scattered radiation. Absorption and attenuation of gamma beams as a function of sample thickness against gamma energy generally exhibit an increasing gamma ray behaviour as the sample thickness increases from 1 to 3 cm. The results showed that the gypsum, kaolin, sand, and clay were capable of attenuating 63.5%, 61.5%, 58.4%, and 44.2 of gamma-ray photons of energy 0.662 MeV at 3 cm thickness %, respectively, and 40.6%, 32.9%, 30.6%, and 27.3% of gamma energy 1.332 MeV at 3 cm thickness, respectively. The results showed that MAC, LAC, and Zeff of all the samples decreased with an increase in photon energy, while those of HVL and TVL increased. The experimental results for all the gamma-ray shielding parameters were found to be in good agreement with the theoretical values obtained using Py-MLBUF. The results have shown that all the samples have similar photon attenuation behaviours; however, gypsum has the best shielding potential than kaolin and this is attributed due to its highest density value.