Exposure Buildup Factor Values Research Articles

Radiation Shielding Features of Glass Fiber Reinforced Cast Polyamide Using Phy-X/PSD and SRIM Software

The utilization of various materials for their nuclear radiation shielding properties has been the subject of a growing number of research and development projects. In this study, the radiation shielding characteristics of E-glass fiber reinforced cast polyamide were evaluated. E-glass is a form of glass fiber frequently utilized as a reinforcement in various composite materials to provide more durability, stiffness, and strength. Samples S1-S7 were defined according to various compositions of E-glass fiber contents (SiO2, Al2O3, B2O3, MgO, CaO, Na2O and K2O) and cast polyamide (C12H22N2O2). Within the energy range 0.015-15 MeV, the shielding parameters: Linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half and tenth value layers (HVL, TVL), mean free path (mfp), effective atomic number (Zeff), atomic and electronic cross sections (ACS, ECS), fast neutron removal cross-section (FNRCS) and exposure buildup factor (EBF) were analyzed. E-glass fiber reinforced cast polyamide S7 (70% glass fiber content) exhibited higher values of LAC, MAC and Zeff and lower values of HVL, TVL, and mfp proving it to be a better radiation shielding material among the samples. An abrupt reduction in values of Zeff was discerned within the photoelectric absorption-dominant region, contrasted with a stable trend within the Compton scattering-dominant region, and a marginal elevation was noted in the pair production region. The maximum and minimum values of FNRCS were observed for samples S1 (10% glass fiber content) and S5 (50% glass fiber content) respectively. Hence, S1 would be the most effective material in fast neutron shielding. At 35 mfp penetration depth, the minimum EBF values belonged to S7 in lower and intermediate regions (0.015-3 MeV) whereas S1 showed the minimum values at higher energy regions (4-15 MeV). Furthermore, the mass stopping power (MSP) and projected range (PR) of the samples for alpha and proton particles were determined using SRIM-2008 codes. S7 exhibited better shielding features for alpha and proton particles with lower values of mass stopping power and projected range. The reinforcement of glass fiber in the cast polyamide has been noticed to have a significant impact on the shielding performance of polymer composites.

Computation of gamma-ray buildup factors for (25-x)CaF2-xAl2O3–15Bi2O3–59B2O3–CuO glasses

High energetic gamma rays are used in different fields and thus it may cause high risks for public if it is absorbed over limited dose. In order to be protected from these hazardous effect of radiation, the shielding is an effective ways and this requires shielding materials. For this purpose the gamma radiation shielding parameters for four different types glasses which was formulated as (25-x)CaF2-xAl2O3–15Bi2O3–59B2O3–CuO (x = 3,6,9,12 mol%) have been investigated. For this purpose, the linear absorption coefficients (LAC, μ) were calculated using Phy-X/PSD within the gamma ray energy range of 10−3-105 MeV. From using the equivalent atomic number (Zeq) and Geometric progression (G–P) method, the exposure buildup factor (EBF) and energy absorption buildup factor (EABF) values were evaluated at 0.015 MeV–15 MeV gamma rays. The values of EBF and EABF were calculated for 1, 5, 10, 20, 30, and 40 cm mean free path (mfp).

Novel slag/natural rubber composite as flexible material for protecting workers against radiation hazards

This work is an attempt to employ the electric arc furnace (EAF) slag as a by-product material to develop an alternative and environmentally friendly material for gamma-radiation protection applications such as in medical and industrial areas. For this purpose, different concentrations of micro-sized EAF slag (0, 20, 40, 60, 80, 100, 500, and 800 phr) were incorporated as fillers in the natural rubber (NR) matrix to produce the shielding composites. In addition, nano-sized EAF slag particles were prepared by using a high-energy ball milling technique to investigate the effect of particle size on the gamma-radiation shielding properties. The synthesized micro and nano EAF/NR composites were tested as protective materials against gamma-radiation by employing NaI(Tl) scintillation detector and standard radioactive point sources (152Eu, 137Cs, 133Ba, and 60Co). Different shielding parameters such as linear and mass attenuation coefficient, half value layer (HVL), tenth value layer, mean free path, effective atomic number (Zeff), and effective electron density (Neff) were determined to assess the radiation shielding capability of the EAF/NR composites. Furthermore, equivalent atomic number (Zeq) and the exposure buildup factor values for photon energy in the range from 0.015 to 15 MeV were also computed by Geometric Progression method. The experimental results of micro EAF/NR composites showed that at 121.78 keV, EAF0 composite (without EAF slag content) had the lowest μ value of 0.1695 cm−1, while the EAF800 composite (which was loaded with 800 phr of micro EAF slag) had the highest μ value of 0.2939 cm−1 at the same energy, which in turn decreases the HVL from 4.09 to 2.36 cm, respectively. Therefore, increasing the filler weight fractions of EAF slag in the NR matrix, increases the shielding properties of the composites. Moreover, the NR composite reinforced with 800 phr of nano EAF slag has better gamma-radiation shielding efficiency compared to that filled with 800 phr of micro EAF slag. The success of this work was to prepare a flexible, lightweight, low-cost, and lead-free material with better shielding capability.

Gamma Attenuation Features of White Cement Mortars Reinforced by Micro/Nano Bi2O3 Particles.

This study aims to explore the radiation protection properties of white mortars based on white cement as a binder and Bi2O3 micro and nanoparticles in proportions of 15 and 30% by weight as replacement sand. The average particle size of micro- and nano-Bi2O3 was measured using a transmission electron microscope (TEM). The cross-sectional morphology and distribution of Bi2O3 within the samples can be obtained by scanning electron microscopy (SEM), showing that nanoscale Bi2O3 particles have a more homogeneous distribution within the samples than microscale Bi2O3 particles. The shielding parameters of the proposed mortars were measured using the HPGe detector at various γ-ray energies emitted by standard radioactive point sources 241Am, 133Ba, 60Co, 137Cs, and 152Eu. The experimental values of the prepared mortars' mass attenuation coefficients (MAC) match well with those determined theoretically from the XCOM database. Other shielding parameters, including half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective electron density (Neff), effective atomic number (Zeff), equivalent atomic number (Zeq), and exposure buildup factor (EBF), were also determined at different photon energies to provide more shielding information about the penetration of gamma radiation into the selected mortars. The obtained results indicated that the sample containing 30% by weight of nano Bi2O3 has the largest attenuation coefficient value. Furthermore, the results show that the sample with a high concentration of Bi2O3 has the highest equivalent atomic numbers and the lowest HVL, TVL, MFP, and EBF values. Finally, it can be concluded that Bi2O3 nanoparticles have higher efficiency and protection compared to microparticles, especially at lower gamma-ray energies.

Investigation of the Influence of TeO2 on the Elastic and Radiation Shielding Capabilities of Phospho-Tellurite Glasses Doped With Sm2O3

The impact of TeO2 on the elastic and radiation shielding properties of phospho-tellurite glasses doped with varying amounts of Sm2O3 has been studied. The elastic properties, such as packing factor, packing density, Young’s modulus, bulk modulus, shear modulus, and Poisson’s ratio, were determined by using the Makashima-Mackenzie and Rocherulle models. The gamma-ray shielding parameters, such as mass attenuation coefficient, half-value layer, tenth-value layer, effective atomic number, equivalent atomic number, exposure buildup factor, and energy absorption buildup factor, were calculated using Phy-X/PSD software in the energy range from 0.015 to 15 MeV at penetration depths up to 40 mean free paths for selected glasses. The fast neutron removal cross section was also determined using Phy-X/PSD software. The results show that the mass attenuation coefficient decreases with increasing photon energy but is not influenced by the addition of Sm2O3. The exposure buildup factor values and energy absorption buildup factors have lower values in the low- and high-energy regions and higher values in the intermediate energy region. The 1.5 mol % concentration of Sm2O3 in the selected glass shows higher exposure buildup factor and energy absorption buildup factor values in the intermediate energy region. Among the selected glasses, PZBTS1.5 has the highest value of fast neutron removal cross sections. The high density, high effective atomic number, and transparency to visible light of these materials indicate that they can be used as shielding materials in nuclear reactors and nuclear technology.

Assessment of the usability conditions of Sb2O3–PbO–B2O3 glasses for shielding purposes in some medical radioisotope and a wide gamma-ray energy spectrum

Abstract We report some fundamental gamma-ray shielding properties and individual transmission factors (TFs) of five distinct glass samples with a nominal composition of xSb2O3·(40 − x)PbO·60B2O3·0.5CuO and (where; 0 ≤ x ≤ 40 mol%). Phy-X/PSD and MCNPX (version 2.7.0) Monte Carlo code are utilized to determine several critical parameters, such as cross-sections, attenuation coefficients, half and tenth value layers, build-up factors, and TFs. A general transmission setup is designed using basic requirements. Accordingly, TFs are evaluated for several medical radioisotopes. Next, the gamma-ray shielding parameters and TFs are assessed together in terms of providing the validity of the findings. Our results showed that there is a positive contribution of increasing Sb2O3 amount in the glass matrix owing its direct effect to the density increment as well. This positive effect on gamma-ray shielding properties is also observed for decreasing mean free path values from S1 to S5 samples. The exposure build-up factor (EBF) and energy absorption build-up factor (EABF) values, increasing the quantity of Sb2O3 supplementation, resulted in a general reduction in EBF and EABF values (i.e., from 0.5 to 40 mfp). When the quantity of Sb2O3 rises from S1 to S5, the collision rate of incoming gamma rays in glass samples increases significantly. The TF figures reveal that S5 showed the least transmission behavior across all the above-mentioned studied glass thicknesses. It can be concluded that increasing the Sb2O3 additive is a beneficial and monotonic technique, when the gamma-ray shielding qualities or TF values must be further enhanced.

A study for gamma-ray attenuation performances of barite filled polymer composites

In this study, radiation protection efficiency (RPE) for the coded as UP-Ba0, UP-Ba25, UP-Ba50, UP-Ba75 and UP-Ba100 at different sample thicknesses, total mass attenuation coefficient (μ/ρ), linear attenuation coefficients (μ), half value layers (HVL), tenth value layers (TVL), mean free paths (MFP), effective atomic numbers (Zeff) and effective electron densities (NE) were determined at various gamma energies between 59.5 and 1408.0 keV. With the help of the geometric progression (G-P) fitting method, the energy absorption build-up factor (EABF) and exposure build-up factor (EBF) values were calculated in the energy range from 0.015 MeV to 15 MeV for the produced composites. HPGe detector and eight radioactive sources (241Am, 152Eu, 137Cs, 133Ba, 60Co, 57Co, 54Mn and 22Na) were utilized in the experiment. Experimental results were compared with theoretical calculations and it has been observed that there is a good agreement between theoretical and experimental results. It was observed that RPE, μ/ρ, μ, Zeff and NE parameters increased with increasing barite amount and decreased with increasing energy, while the opposite situation was observed in HVL, TVL and MFP parameters. EABF and EBF values increase with increasing penetration depth. As a result, UP-Ba100 is a good radiation absorber according to the other studied barite filled polymer composites.

Computation of Gamma Buildup Factors and Heavy Ions Penetrating Depths in Clay Composite Materials Using Phy-X/PSD, EXABCal and SRIM Codes

Most investigations of the gamma-shielding abilities of materials are often based on the Beer-Lambert law including recent studies on clay-polyethylene composites. The findings are usually silent on the secondary radiation effects that commonly occur due to photon buildup, known as Energy Absorption Buildup Factor (EABF) and Exposure Buildup Factor (EBF). In this work, the computation of EABF and EBF in the region of energy 0.015–15 MeV at different penetration depths or mean free paths up to 40 mfp—and simulation of 100 keV of Cs and Sr ion-penetration profiles of clay–polyethylene composites (A–G) containing 0–30 wt% low density polyethylene (LPDE)—was carried out. The buildup factors computation was performed using Phy-X/PSD and EXABCal codes, and the ion-penetrating profile was studied using a Monte Carlo simulation code called Stopping and Range of Ions in Matter (SRIM). The EABF and EBF values are functions of the photon energy and the penetration depth. In the region of intermediate energy, the EABF and EBF values are higher for each of the samples. For a given mfp, the peak value of either EBF or EABF of each sample increases with LDPE wt% in the clay matrix. The projected range of both Cs and Sr ions in the samples decreased with increasing sample bulk densities, with Cs having a higher projected range than Sr in all the samples. The Cs and Sr ions have the lowest respective projected ranges in sample A (of bulk density 2.03 g·cm−3; 0 wt% of LDPE), while the highest projected ranges were recorded in sample G (of bulk density 1.34 g·cm−3; with 30 wt% of LDPE), respectively. This study reaffirmed the suitability of clay composite for gamma-ray shielding applications; however, it may not yet be ready to be used as a backfill material to mitigate the migration of fission products present in radioactive nuclear wastes.

Monte Carlo calculation of buildup factors for 50 keV–15 MeV photons in tungsten up to 15 mean free paths

Exposure buildup factor values of tungsten for a point isotropic source in energy range 0.05–15 MeV up to 15 mfp are computed using Monte Carlo N-Particle code. Buildup factors of this study and ANSI/ANS-6.4.3 at some selected energies and penetration depths are compared. Highest discrepancies are observed for high-energy and/or high penetration depths. Highest error occurs at 15 MeV, amounting to 32%. In the energy range 2–6 MeV, our results show smaller values for all penetration depths and vice versa at higher energies.

Evaluation of radiation attenuation properties of some cancer drugs

The present study was conducted to estimate the radiation attenuation parameters of six different antineoplastic drugs used in the cure of cancer diseases. The effective atomic number and electron density of anastrozole, epirubicin, gemcitabine, ifosfamide, methotrexate and paclitaxel were computed theoretically in the energy region of 1keV to 100 GeV. The energy absorption buildup factors (EABF) and exposure buildup factors (EBF) for these chemotherapy drugs were also examined by applying GP-fitting method. The variation of EABF and EBF values with photon energy and penetration depth were presented graphically and discussed. The results obtain from this study pointed out that buildup factors rely on the chemical combination of the drugs, incident photon energy and penetration thickness. It was observed that ifosfamide had a significantly better radiation absorption effect compared to other drugs. The data obtained from this study are expected to be useful in the fields of radiation biology, radiation dosimetry and radiotherapy.

Radiation protection assessment of gamma photons in 64TeO2–10WO3–10Nb2O5– 15KF–1La2O3 glasses doped with Tm2O3 using photon-shielding and dosimetry software

Radiation-shielding applications are necessary to protect against deleterious effects of radiation. This study tested thulium oxide (Tm2O3) added to the glass-system composition 64TeO2–10WO3–10Nb2O5–15KF–1La2O3. Adding Tm2O3 increased sample density from 5.22 to 5.40 g/cm3 and measured at photon energy of 15 keV–15 MeV. Multiple radiationshielding parameters were evaluated and assessed using photon-shielding and dosimetry software, including linear and mass attenuation coefficients, half-value layers, mean free paths, atomic and electronic cross sections, effective atomic numbers, effective electron density, and exposure buildup factors. Half-value layer and mean free-path values were compared with those of well-known radiation-shielding materials, ie, conventional concrete and commercial glasses. Atomic and electronic cross-section values effectively increased with the addition of thulium oxide to the glass systems. While the highest linear and attenuation coefficients were 242–281 cm2 /g at 15 keV, the denser glass recorded the highest mass attenuation coefficients value of 52.17 cm2 /g across all samples. The highest effective atomic number and effective electron density were recorded for the denser glass, because it had the highest thulium oxide fraction and was more burdened by interaction with photon energy. Half-value layers and mean free paths showed similar behavior, and high-density materials achieved low values. At high energy, exposure buildup-factor values increased, while at low energy, values decreased.

Impact of TiO2 on radiation shielding competencies and structural, physical and optical properties of CeO2–PbO–B2O3 glasses

The glasses of series xTiO2-xCeO2-(30-x) PbO-(70-x) B2O3 where 2 ≤x ≤ 10 mol% were made using conventional melt-quench method and X-ray diffraction technique has been used to ascertain the amorphous nature of these glasses. The analysis of the compositional dependence of the physical parameters like density, molar volume and oxygen packing density along with the elastic parameters (Young's modulus, shear modulus, Vickers hardness number) of the studied glasses has been done. Infrared (IR) spectra revealed BO3 and BO4 units as main glass forming groups in these glasses but at higher concentrations of TiO2, Ti3+ and Ti4+ ions get significantly incorporated in glass matrix thereby creating TiO4 and TiO6 structural units. Optical spectral studies indicated that the band gap energy values decreased with increasing TiO2 content and these glasses had good UV-blocking efficiency which could be exploited for their use as transparent UV shielding materials. The radiation shielding parameters such as Half Value Layer, Linear Attenuation Coefficient, Exposure Buildup Factor, Mean Free Path including thermal and fast neutron cross section were deduced which indicated that the attenuation performance of these glasses improved with the addition of TiO2. Lower values of Exposure Buildup Factor and higher values of thermal and fast neutron removal cross section reflect the proficient shielding ability of these glasses.

Physical, neutron, and gamma-rays shielding parameters for Na2O–SiO2–PbO glasses

The present study investigated the physical and neutron- and gamma-ray-shielding features of a sodium oxide (Na2O)-doped lead (Pb)–silicate glass system. The chemical composition of the glass system is described by the formula xNa2O–50SiO2·(50 − x)PbO, where x = 0, 10, 20, 30, 40 and 50 mol%. Moreover, the shielding features were investigated by utilizing the Geant4 simulation code and the Xcom program. The density of the glasses (ρglass) was enhanced from 2.460 to 6.995 g/cm3. The mass attenuation coefficient (MAC, μ/ρ) was calculated. The MACs were arranged in the order of (NSP50)MAC> (NSP40)MAC> (NSP30)MAC> (NSP20)MAC> (NSP10)MAC> (NSP0)MAC. The half-value layer varied from 14.23 to 2.55 cm for NSP0 to NSP50, respectively, at 0.015 MeV. The mean free path (MFP) values ensured the shielding capacity for NSP-glasses, as it was found to possess the shortest MFP, and its value at 0.015 MeV changed from 20.53 to 3.68 cm for NSP0 and NSP50, respectively. The NSP50 glass sample has the highest Zeff, which increased from 32.70 to 76.93. The calculated exposure buildup factor values were greater than those of the energy absorption buildup factor at fixed energy and penetration depth for all studied glasses. The fast neutron removal cross-section ∑R(cm−1) increased gradually with the increase in lead (II) oxide content. Finally, one can conclude that the investigated NSP0–NSP50 glasses are superior materials for neutron and γ-ray shielding.

The photon interactions and build-up factor for gadolinium sodium borate glass: Theoretical and experimental approaches

Gadolinium sodium borate glass in compositions of xGd2O3: 20Na2O:(80-x)B2O3 (where x is 0, 5, 10, 15, and 20 mol%) were prepared by melt quenching technique. The glass samples have been investigated for the physical properties and radiation shielding properties. The glass density and molar volume tended to increase with increasing Gd2O3 concentration. The theoretical values of radiation shielding were computed by WinXCom program in the energy range 0.015 MeV–15 MeV. The experimental values have been measured in energy range 0.223 MeV–0.662 MeV using Compton scattering technique for variation the energy from Cs-137 source. The experimental values are in good agreement with the theoretical values. From the results, the replacement of B2O3 by Gd2O3 helped to increase the mass attenuation coefficients (μm), effective atomic number (Zeff) and effective electron density (Neff). The energy absorption buildup factor coefficients (EABF) and the exposure buildup factor values (EBF) were decreased with the increasing of Gd2O3 at energy below 2 MeV and show the increase with Gd2O3 content at energy higher than 2 MeV. The half value layer (HVL) were decreased with increasing of Gd2O3. All studied glasses were found to be lower HVL values, when compared with the some standard shielding materials. These results reflected to the ability of gadolinium sodium borate glass for radiation shielding material.

Coconut Dust Gypsums Board Building Material for Shielding Radiation and Buildup Factors

The coconut dust gypsums were fabricated and investigated through shielding radiation properties, energy absorption buildup factor (EABF), and exposure buildup factor (EBF). The mass attenuation coefficient (mm) was investigated by using the Compton scattering technique at energy 662 keV and theoretical values of the mass attenuation coefficients were computed by using the WinXCom software program at different photon energies from 1 keV - 100 GeV. EABF and EBF values were computed by the Geometric Progression (G-P) fitting method at photon energies ranging between 0.015 and 15 MeV up to deep penetration of 40 mean free path (mfp). After the addition of coconut dust volume into gypsum board, it was found that mm values of the experiment and theory were generally in a good agreement. The results also indicated that the mm increased while the EABF and EBF decreased along with the increase in the coconut dust volume. The EABF and EBF values with photon energy and deep penetration for coconut dust gypsums were found at a minimum value, i.e., at low and high energy range whereas, at the intermediate energy range, it could become high. These results suggest that coconut dust gypsums can be used as shielding radiation building material.

Exposure buildup factor investigation of tungsten gadoliniumborate system

Abstract The gamma ray exposure buildup factors (EBF) of xWO3:(70-x)Gd2O3:30B2O3 system (where x=40, 45, 50, 55 and 60 mol%) have been calculated in the energy region 0.015–15 MeV up to a penetration depth of 40 mfp (mean free path). The five parameter geometric progressions (G-P) fitting method has been used to compute exposure buildup factor values. Variation of exposure buildup factors with incident photon energies and penetration depth have been studied. It was found that EBF values were higher in the intermediate energy region, for all glass system. Moreover, tungsten gadolinium borate glass of 40 mol% WO3, was found to present the lowest EBF values, hence it is excellent gamma ray shielding material. The obtained results in this paper show that these glasses can be used as radiation shielding materials

SnO-reinforced silicate glasses and utilization in gamma-radiation-shielding applications

The influence of tin (II) oxide (SnO) on the γ-ray radiation-protection characteristics of binary silicate glass samples with the form (100 − x)SiO2–xSnO, 40 mol% ≤ x ≤ 60 mol%, was investigated. The density and molar volume of the glasses were determined. The values of μ/ρ (mass attenuation coefficients in cm2/g) of the investigated glasses were evaluated by using the XCOM software and Monte Carlo N-Particle Transport 5 simulation in the energy range of 0.015–15.000 MeV. The obtained values of μ/ρ show good agreement between the two methods. In terms of μ/ρ, several gamma ray protection parameters, such as half-value layer, mean free path, effective atomic number, exposure build-up factor (EBF) and energy absorption build-up factor (EABF), were calculated. The results revealed that the μ/ρ values of all samples can be arranged in the order SiSn60 > SiSn55 > SiSn50 > SiSn45 > SiSn40. The results showed that the half-value layers of the investigated samples were in the order SiSn40 > SiSn45 > SiSn50 > SiSn55 > SiSn60. The values of EBF and EABF show proportionate variations with the photon energy and chemical composition of the glasses. Therefore, the investigated glasses can be considered satisfactory materials for gamma ray protection, particularly the SiSn60 sample, with 60 mol% tin (II) oxide.

Iron (III) oxide doped lithium borate glasses: structural and charged particles/photon shielding properties

The elemental composition and surface morphologies of the (Li2B4O7) (100-x) - (Hematite) x glass samples (here x = 10,20, 30 and 40% weight) were acquired by SEM/EDX measurements. Using the EDX results, the mass attenuation coefficient (µ/ρ in units of cm2/g) of the glasses were generated with MCNPX simulation codes and calculated by XCOM software. Both results were matched by utilizing relative deviations. Next, Half Value Layer (HVL), Effective Atomic Number (Zeff), Mean Free Path (MFP), Exposure Buildup Factors (EBF), Energy Absorption Buildup Factors (EABF), Fast Neutron Removal Cross Sections (ΣR) and Relative Dose Distribution (RDD - for gamma and neutron) were calculated. Mass Stopping Power (MSP) and Projected Range (PR) values were calculated to examine the proton and alpha shielding properties of the hematite doped glass samples. According to the results obtained, µ/ρ, Zeff, and ΣR values increase as the percentage of hematite mineral in the glass samples increases. In addition, it was observed that HVL, MFP, EBF, EABF and RDD values decreased with increasing hematite percentage. The increase in the rate of hematite in the glass provided alpha and proton particles to have shorter ranges. Among the studied glass samples, lithium borate glass with 40% hematite mineral ratio is the sample with the best gamma, neutron and charged particles shielding features.

Estimation of gamma-rays, and fast and the thermal neutrons attenuation characteristics for bismuth tellurite and bismuth boro-tellurite glass systems

Gamma-rays and fast and thermal neutron attenuation features of (Bi2O3)x–(TeO2)(100−x) (where x = 5, 8, 10, 12, and 15 mol%) and [(TeO2)0.7–(B2O3)0.3](1−x)–(Bi2O3)x (where x = 0.05, 0.10, 0,15, 0.20, 0.25, and 0.3 mol%) glass systems have been explored and compared. For all samples, mass attenuation coefficients (μ/ρ) are estimated within 0.015–15 MeV photon energy range by MCNP5 simulation code and correlated with WinXCom results, which showed a satisfactory agreement between computed μ/ρ values by these both methods. Additionally, effective atomic number (Zeff), effective electron density (Neff), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), total atomic cross-section (σa), and total electronic cross-section (σe) are calculated by utilizing μ/ρ values. The μ/ρ, Zeff, and Neff are energy dependent and have higher values at the lowest energy and smaller values at higher energies. Moreover, using the G–P fitting method as a function of penetration depth (up to 40 mfp) and incident photon energy (0.015–15 MeV range), exposure buildup factors (EBFs) and energy absorption buildup factors (EABFs) are evaluated. Both 85TeO2–15Bi2O3 (mol%) and 49TeO2–21B2O3–30Bi2O3 (mol%) samples, by possessing higher values of Zeff, exhibit minimum EBF and EABF values. Highest μ/ρ, Zeff values and lowest HVL, TVL, MFP values of 49TeO2–21B2O3–30Bi2O3 (mol%) sample indicated its better gamma-ray absorption capability among all selected glasses. Further, macroscopic effective removal cross-section for fast neutrons (ΣR), coherent scattering cross-section (σcs), incoherent scattering cross-section (σics), absorption cross-section (σA), and total cross-section (σT) values for thermal neutron attenuation have been computed. Among all samples, 49TeO2–21B2O3–30Bi2O3 (mol%) glass possesses a better ΣR value for fast neutron attenuation, while the largest ‘σT’ value of 66.5TeO2–28.5B2O3–5Bi2O3 (mol%) sample suggests its good thermal neutron absorption efficiency.

B2O3–Bi2O3–TeO2–BaO and TeO2–Bi2O3–BaO glass systems: a comparative assessment of gamma-ray and fast and thermal neutron attenuation aspects

For Pb-free 35B2O3‒35Bi2O3‒(30–x)TeO2‒(x)BaO (x = 5, 10, 15, 20, and 25 mol%) and (90–x)TeO2‒10Bi2O3‒(x)BaO (x = 10, 15, and 20 mol%) glass systems, gamma and neutron (both fast and thermal neutron) radiation shielding features were examined and compared. Within 0.015–15 MeV photon energy, mass attenuation coefficients (μ/ρ), for all samples, which have been assessed using WinXCOM program are in fair agreement with deduced MCNP5 simulation code μ/ρ results. For all selected samples, at the lowest energy, μ/ρ has bigger values whereas at higher energy regions possess lower values. Furthermore, by employing μ/ρ values, effective atomic number (Zeff), effective electron density (Neff), half-value layer (HVL), tenth-value layer (TVL), and mean free path (MFP) are figured out for both glass systems. For studied samples, with the gradual replacement of TeO2 content with BaO, the derived values of Zeff, HVL, TVL, and MFP revealed improved γ-ray shielding potentiality. Besides, within photon energy range of 0.015–15 MeV, exposure build-up factors (EBFs) and energy absorption build-up factors (EABFs) were estimated for all samples by utilizing G‒P fitting method as a function of different penetration depths (0.5, 1, 2, 3, 4, 5, 6, 7, 8, 10, 15, 20, 25, 30, 35, and 40 mfp). The 35B2O3–35Bi2O3–5TeO2–25BaO (mol%) glass relatively larger μ/ρ and Zeff values, lower HVL, TVL, and MFP values, and minimal EBF and EABF values confirm its superior γ-ray attenuation competence among all samples. Additionally, in comparison, HVL and MFP values of 35B2O3–35Bi2O3–5TeO2–25BaO (mol%) sample are lower than the respective values of some commercial γ-ray shielding glasses and different types of standard concretes, signifying its better shielding features than them. Moreover, macroscopic removal cross-section for fast neutrons (ΣR), coherent scattering cross-section (σcs), incoherent scattering cross-section (σics), absorption cross-section (σA), and total cross-section (σT) for thermal neutrons absorption were derived for both glass systems. Among all selected glasses, 35B2O3–35Bi2O3–5TeO2–25BaO (mol%) sample possesses relatively higher ΣR (0.106 cm−1) and ‘σT’ (8.809 cm−1 at 0.0253 eV neutron energy) values for fast and thermal neutrons attenuation, respectively, demonstrating its favorable absorption capability for neutrons.