Linear Attenuation Coefficient Values Research Articles

Physical, structural and nuclear radiation shielding behaviour of xBaO-(0.30-x)MgO-0.10Na2O-0.10Al2O3-0.50B2O3 glass matrix

In the present investigations, six cylindrical shaped glass sample having chemical composition x BaO-(0.30-x) MgO-0.10Na2O-0.10Al2O3-0.50B2O3 (x = 0.05, 0.10, 0.15, 0.20, 0.25 and 0.30 mol fraction) were prepared by melt quenching technique. The density, molar volume, oxygen packing density (OPD), oxygen molar volume (OMV), Poisson's ratio, barium inter ionic distance, Polaron radius and field strength were calculated for the prepared glass samples. The values of linear attenuation coefficients (LAC) were measured experimentally by using narrow beam transmission geometry in the gamma photon energy range of 59.54–1332 keV. In order to ascertain the application of the prepared glasses in the field of radiation protection and design, the values of LAC were used to calculate various gamma ray interaction parameters namely half value layer (HVL), Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), effective atomic number (Zeff), electron density (Ne) and Exposure Buildup Factors (EBFs). The values of fast neutron removal cross sections (∑R cm−1) were also calculated for the prepared glass matrix. The theoretical values of attenuation parameters were determined using online software Phy-X/PSD and FLUKA (Monte-Carlo) simulation code. Excellent agreements have been observed between experimental, theoretical and simulation results for the prepared glass samples. Furthermore, the radiation shielding properties for the prepared glass samples were compared with conventional used concretes and commercial radiation shielding glass (RS253 G-18). On the basis of the obtained results, it has been reported that the prepared glass samples possess satisfactory physical reliability and superior shielding efficiency against gamma rays and fast neutrons as compared to conventional/commercial shielding materials.

Investigations on physical, structural and nuclear radiation shielding behaviour of niobium–bismuth–cadmium–zinc borate glass system

In the present paper, glass sample with the chemical composition xNb2O5+0.20Bi2O3+0.20CdO+0.10ZnO+ (0.50-x)B2O3 (where x = 0.05, 0.10, 0.15, 0.20, 0.25 mol fraction) were prepared by melt quenching-annealing technique. The density, molar volume, oxygen molar volume (OMV) of the glass samples are found to increase increases from 5.35 to 5.65 gcm−3, 32.69–37.32 cm3/mole, 14.323–14336 cm3/mole, respectively, with the increase in molar concentration of Niobium pentoxide. The value of Poisson's ratio shows a very small variation in the range of 0.240–0.247 for the present glass matrix, however these results confirms that the prepared glass samples have high cross link density. The linear attenuation coefficients were measured experimentally by employing narrow beam transmission geometry (total scatter acceptance angle = 2.22°) with NaI(Tl) spectroscopy in the gamma photon energy range of 59.54–1332 keV. These values of linear attenuation coefficient were then further used to calculate other attenuation parameters namely Half Value Layer (HVL), Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), effective atomic number (Zeff), electron density (Ne) and Buildup Factor (BF). Measured values of attenuation parameters have also been compared the values obtained theoretically using online software Phy-X/PSD and Py-MLBUF as well as with values obtained through FLUKA (Monte-Carlo) simulations code. Excellent agreements have been observed between experimental, theoretical and simulation results for the prepared glass samples. In addition to this, fast neutron removal cross sections (∑R cm−1) were calculated for the glass matrix under investigations. On the basis of the obtained results, it has been reported that the prepared glass samples possess superior shielding efficiency against gamma rays and fast neutrons as compared to conventional shielding materials.

Comparing basic radiation attenuation factors of tellurite glasses containing PbCl2 and Bi2O3 with some other potential glass systems

In this work, we have compared the radiation shielding properties of tellurite glasses containing PbCl2 and Bi2O3 with some other potential glass systems at 0.662 MeV. The linear attenuation coefficients (LAC) for the selected glasses was compared with those reported previously for Bi2O3-Na2O-B2O3 glass system. We found that 70TeO2-15PbCl2-15Bi2O3 and 70TeO2-10PbCl2-20Bi2O3 glasses have higher LAC values than all the Bi2O3-Na2O-B2O3 glasses, while the LAC value of 90TeO2-5PbCl2-5Bi2O3 is very close to that of 30Bi2O3-20Na2O-50B2O3. Also, the LAC values for present glasses was compared with those of PbO-Al2O3-SiO2 glasses. Among our selected glasses, 70TeO2-15PbCl2-15Bi2O3 has same LAC as that reported for 0.5PbO-0.1Al2O3-0.4SiO2 glass. We also have compared the LAC values of the tellurite glasses containing PbCl2 and Bi2O3 glasses with B2O2-Na2O-Bi2O3-WO3 glass system, and we found that the LAC for 90TeO2-5PbCl2-5Bi2O3 glass is close to LAC of 0.55B2O2-0.2Na2O-0.2Bi2O3-0.05WO3 glass. The effective atomic number (Zeff) of the present glasses was compared with the values reported for Bi2O3-SiO2-Al2O3 glass system at 0.662 MeV. The results demonstrated that the selected glasses have lower Zeff values ranging between 28.12 and 35.04, and these values are values less compared to Zeff of all the glasses in Bi2O3-SiO2-Al2O3 system. The selected glasses were found to be better shielding agents than PbO-WO3-Na2O-MgO-B2O3 glasses. In terms of half value layer, the selected glasses were compared with other glasses doped with heavy metal oxides and we found that all the selected glasses (except the sample with composition of 90TeO2-5PbCl2-5Bi2O3) exhibit lower range of HVL than PbO-Sb2O3-B2O3-Gd2O3 glasses.

The Influence of CoO/P2O5 Substitutions on the Structural, Mechanical, and Radiation Shielding of Boro-Phosphate Glasses.

A new glass system (50−x)P2O5–20B2O3–5Al2O3–25Na2O–xCoO was manufactured using a standard melt quenching procedure, where 1≤ x ≤ 12 mol%. The characteristics of boro-phosphate-glasses containing CoO have been studied. The effect of CoO on the radiation-protective properties of glasses was established. The density of the prepared glasses as a function of CoO increased. XRD was used to check the vitreous structure of samples. Fourier-transform infrared (FTIR) spectroscopy was used to study the structure of each sample. FTIR demonstrated that connections grew as CoO/P2O5 levels increased, and the FTIR spectra shifted to higher wavenumbers. The increment of CoO converts non-bridging oxygens associated with phosphate structural units into bridging oxygens. This process increases the concentration of BO4 structural units and creates new, strong and stable bonds B–O–P, i.e., there is polymerization of the boro-phosphate glass network. With an increase in the ratio of CoO/P2O5 in the produced samples, ultrasonic velocities and elastic moduli were observed to increase. The coefficients of linear and mass attenuation, the transmittance of photons in relation to the photon energy, the efficiency of radiation protection in relation to the photon energy, and the thickness of the absorber were modeled using these two methods (experimental and theoretical). From the obtained values, it can be concluded that the 12Co sample containing 12 mol% will play the most influential role in radiation protection. An increase in the content of cobalt-I oxide led to a significant increase in the linear and mass attenuation coefficient values, which directly contributes to the development of the radiation-protective properties of glass.

Experimental and theoretical analysis of radiation shielding properties of strontium-borate-tellurite glasses

The aim of this investigation is to analyse the radiation shielding features of a SrO–B2O3–TeO2 glass system. The glasses have the composition of 10SrO-(90-X)B2O3-XTeO2, where X is equal to 40, 45, 50, 55, and 60 mol%. The mass attenuation coefficients (MAC) of the samples were experimentally determined and were validated with results obtained using the Phy-X/PSD software. Narrow beam transmission geometry was utilized to obtain the experimental MAC values. When comparing the experimental and theoretical values, the results were found to strongly agree with each other. Using the MAC values, the linear attenuation coefficients (LAC) of the glasses were determined. The results demonstrated that the LAC values decrease with increasing energy, meaning that the glasses are more effective against lower energy photons. The radiation protection efficiency (RPE) showed that increasing the TeO2 content in the glasses improves the shielding ability of the glasses. The HVL and MFP were next calculated and the SBT60 sample showed to have the lowest values at all energies, while having the greatest Zeff and Neff. Lastly, the MFP results for the SBT60 glass were compared against other common radiation shields and it was demonstrated that the sample outperformed most of the shields it was compared against. Therefore, it was concluded that the SBT60 glass has great potential as an environmentally friendly shield for radiation applications.

Analysis of physical and mechanical traits and nuclear radiation transmission aspects of Gallium(III) trioxide constituting Bi2O3-B2O3 glasses

For five Ga2O3-Bi2O3-B2O3 composition glasses for improved Bi2O3 content at 25 to 65 mol% (10% continuously each time) at a fixed 10 mol% Ga2O3 amount, distinct physical and mechanical aspects and nuclear radiation attenuation factors were investigated. Increased Λ (optical basicity) values with a gradual Bi2O3 addition indicate studied samples’ improving basic character. Applying BC (bond compression) model key mechanical traits such as Ybc (Young’s modulus), Kbc (bulk modulus), S (shear modulus), L (longitudinal modulus), and σ (Poisson’s ratio) are evaluated where in all glasses 10Ga2O3-65Bi2O3-25B2O3 (mol%) sample exhibits superior elastic moduli. Enhanced Bi2O3 causes for compactness of the gallium borate network as ǹc (average cross-link density) improves from 2.3 to 3.4 indicating increased rigidity of glasses. Later, PHITS, FLUKA, and MCNPX codes are wielded to derive μ/ρ (mass attenuation coefficient) of all selected samples for photons having energy ranging from 15 KeV to 15 MeV. Simulated μ/ρ quantities exactitude is tested via Phy-X/PSD and WinXCOM programs’ μ/ρ results and identified a fairly good harmony among them. With photon energy, MFP (mean free path), TVL (tenth-value layer), and HVL (half-value layer) values variations show a similar tendency and against the trend which noticed for μ/ρ and μ (linear attenuation coefficient) values. 10Ga2O3-65Bi2O3-25B2O3 (mol%) sample’s MFP and HVL are correlated with five commercial γ-ray glass shields’ respective values at 1.25 MeV, 0.662 MeV (137Cs), and 0.2 MeV energies. Further, Zeq (equivalent atomic number) and using G–P (geometric progression) fitting approach for ten individual PDs (penetration depths) within 1–40 mfp range at 15 – 15 × 103 KeV energy region BUFs (buildup factors) were estimated. Attained RPE (radiation protection efficiency) findings attest all chosen Ga2O3-Bi2O3-B2O3 glasses’ competent absorption capacity for lower energy photons. Next, α-particles and protons MSPs (mass stopping powers), i.e. ΨA and ΨP and PRs (projected ranges), i.e. ΦA and ΦP by utilizing SRIM code as well as for electrons MSPs (ΨE) and CSDA (continuous slowing‐down approximation) ranges by ESTAR database have been calculated within 15–15 × 103 KeV KE (kinetic energy) range. Also, ΣR (fast neutron removal cross-section) and for 0.253 × 10–4 KeV energy neutrons σT (total cross-section) and SP (shielding percentage) values were approximated. With Bi2O3 addition, realized ΣR is changed at 0.1161–0.1213 cm−1 extent. For thermal neutrons absorption, 10Ga2O3-25Bi2O3-65B2O3 (mol%) glass shows larger σT (=17.534 cm−1) and at any considered thickness higher SP whereas 10Ga2O3-65Bi2O3-25B2O3 (mol%) (lead-free) glass has better attenuating features for photons affirming the incorporated Bi2O3 favorable effect.

Lead–bismuth tungstate composite as a protective barrier against gamma rays

The expanded use of radiations in diagnosis therapy, energy sectors, and various industries caused considerable concerns resulting from the increased exposure to ionizing radiations. Therefore, a series of tungsten-based composites (Bi2WO6, PbWO4, and Pb0.82Bi0.12WO4/W0.5Pb0.5Bi12O20) were synthesized, through One-Pot Hydrothermal Route, as effective protective barriers against gamma rays (γ-rays). The synthesized composite materials were characterized by XRD, Raman spectrometry, SEM-EDX-mapping, and density measurements. Various parameters were experimentally measured to determine the composites' viability as radiation shields, including linear attenuation coefficient (LAC), enhancement ratio, radiation protection efficiency, half-value layer, and mean free path. The narrow beam experimental gamma-photon transmission method was used to estimate the LAC's values for the synthesized composites using Cs-137 (with energies of 0.662 and 1.173 MeV) and Co-60 isotopes (with energy of 1.332 MeV). Among the investigated novel composites, the ternary composite (Pb0.82Bi0.12WO4/W0.5Pb0.5Bi12O20) proved to be the most efficient radiation shield. The MCNP-5 Monte Carlo simulation code and XCOM theoretical calculations data were in excellent harmony with the obtained experimental findings. The obtained results confirmed a strong relationship between the synthesized composites' chemical composition and their shielding capacity, where the ternary synthesized composite Pb0.82Bi0.12WO4/W0.5Pb0.5Bi12O20 with high lead-bismuth content has the highest LAC among the synthesized composites.

Nuclear radiation shielding characteristics and physical, optical, mechanical, and thermal properties of lithium-borotellurite glass doped with Rb2O

The current paper addresses the influence of Rb2O in the lithium-borotellurite (LBT) glass system for the first time. For this, the glass system (25-x)Li2O–15B2O3–60TeO2-xRb2O was designed where x: 0, 5, 10, 15, 20, and 25 mol%. An extensive investigation was carried out to understand the alterations in physical, optical, thermal, and mechanical properties with the use of theoretical calculations. The user-friendly Phy-X/PSD software was employed to demonstrate the nuclear radiation protection properties. From physical property calculations, the addition of Rb2O from 0 to 25 mol% increased average molecular weight (AMW) from 113.68 to 152.94 g mol−1 and glass density (ρglass) from 4.2743 to 4.7710 g cm−3. Likewise, molar volume (Vm), oxygen molar volume (VO), oxygen packing density (OPD), and number of bonds per unit volume (nb) were considerably changed by the increasing Rb2O concentration. According to the optical calculations, the refractive index (n) increased from 2.3348 to 2.6104, while the dielectric constant (ε) increased from 5.45 to 6.81. Moreover, the metallization criterion (M) showed a decreasing trend, and implied increasing insulation with the increase in Rb2O in the glass system. For thermal property estimations, viscosity versus temperature profiles clearly indicated that all R-series have the ability to form glass, but decreasing the Li2O caused an increment in glass melting temperature. The mechanical moduli determinations via the Mackenzi-Makishima model demonstrated that Young's (E), bulk (B), shear (S), and longitudinal (L) moduli were gradually decreased by introducing Rb2O into the glass network. From the perspective of radiation shielding calculations, the essential parameter, linear attenuation coefficient (LAC), effectively improved by increasing the doping rate of Rb2O. Based upon the LAC values, the other critical parameters such as mean free path (MFP), half-value layer (HVL), and effective atomic number (Zeff) were successfully evaluated. Additionally, build-up factors such as exposure (EBF) and energy absorption (EABF) were assessed with the implementation of G-P progression. They showed that sample-R25 ensured better gamma-ray shielding properties compared to the other samples. Lastly, fast neutron removal cross-section (FNRCS) determinations displayed decreasing behaviour with the increasing Rb2O content, which is not convenient for effective neutron shielding abilities. All in all, the Rb2O-reinforced borotellurite glass can serve as an alternative radiation shielding material.

Optical and gamma ray shielding properties BaO doped K2O-TiO2-P2O5 glasses

The optical and gamma ray shielding characteristics of (20-x) K2O-xBaO-30TiO2-50P2O5 glasses were shown to be affected by the addition of BaO. The optical band gap energy are increases, refractive index shows a small decrement with addition of BaO in the phosphate-based glasses. With the substitution of BaO, the two parameters, molar refractivity and molar electronic polarizability are both decreased. Reflection loss (RL) is known to range from about 0.171 to 0.153, whereas transmission (T) is reported to fall between 0.7078 and 0.7339. When BaO is added to the oxide ion matrix, the polarizability of the oxide ions increases. The manufactured glass systems have a metallisation of less than one, suggesting that they are non-metallic in nature. The linear attenuation coefficient (LAC) of the tested glasses is investigated between 0.0395 MeV and 0.411 MeV. The LAC values also follow the order of KBTP20 > KBTP15 > KBTP10 > KBTP5 > KBTP0. The glass with composition of 20 BaO-30 TiO2-50 P2O5 has the greatest LAC. The effective atomic number of the KBTP10 sample is equal to 36.66 at 0.0395 MeV, and decreases to 35.35, and 12.27 at 0.0395 MeV and 0.4111 MeV, respectively. The half value layer values at 0.1218 MeV lies within 0.564 and 1.644 cm. The results proved that increasing the BaO content in the glass system leads to more desirable radiation shielding properties for the samples.

Fabrication, structural, optical, and dielectric properties of PVC-PbO nanocomposites, as well as their gamma-ray shielding capability

Physical, linear optical, dielectric spectroscopy and photon shielding competence of fabricated PVC (polyvinyl chloride) doped with xPbO nanoparticles (x = 0, 2.5, 5, 10, 15, and 25 wt%) have been investigated. The density of PVC is increased from 1.4451 to 2.1014 g cm−3 by incorporation 25 wt% of PbO. The optical band gap (Egap) decreases from 5.14 to 4.54 eV for the direct transition and from 4.50 to 3.75 eV for the indirect transition as the concentration of PbO increases. Urbach energy (Eurbach) increased from 0.198 eV for the pure PVC sample to 0.673 eV for PVC loaded with 25 wt% of PbO. Refractive index (n) increased with the increase of PbO concentration. The less dielectric constant (ε′) values of all nanocomposites were obtained than that for pure PVC. Values of dielectric loss (tan δ) for all investigated samples decreases with increasing frequency up to 50 kHz and become constant for further frequency. Both linear (LAC) and mass attenuation coefficients (MAC) values of PVC were gradually increased by increase concentration of PbO while both half value layer (HVL) and relaxation length (RL) value were gradually decreased by increase concentration of PbO. Pure PVC with density (ρ = 1.4451 g cm−3) has neutron shielding characteristics better than that obtained for PVC/25 wt% PbO with higher density (ρ = 2.1014 g cm−3). The highest ∑R is 0.06252 cm2 g−1 for pure PVC, and the lowest is 0.05003 cm2 g−1 for PVC/25 wt% PbO, in contrast. Finally, the obtained results confirm that the fabricated PVC-PbO nanocomposites can be applied in optical, electronic, and radiation shielding applications.

Newly Developed Vanadium-Based Glasses and Their Potential for Nuclear Radiation Shielding Aims: A Monte Carlo Study on Gamma Ray Attenuation Parameters.

This study aimed to investigate different types of glasses based on the 46V2O5-46P2O5-(8-x) B2O3-xCuO system in terms of their nuclear radiation shielding properties. Accordingly, five different CuO-doped vanadate glasses were investigated extensively to determine the necessary gamma shielding parameters along with effective conductivity at 300,000 and buildup factors. Phy-x PSD software was used for determination of these vital parameters. Furthermore, these parameters, such as half value layer, tenth value layer, and mean free path were investigated in a broad energy range between 0.015 and 15 MeV. The results revealed that the amount of CuO reinforced in each sample plays an essential role in determination of the shielding abilities of the samples. The sample with the highest CuO content had the highest linear attenuation coefficient and mass attenuation coefficient values. Additionally, the lowest mean free path, half value layer, and tenth value layer values were recorded for glass sample VPCu8. There was an inverse relation between the effective conductivity and effective atomic number and photon energy; that is, as energy increases, the effective conductivity and effective atomic number decreased rapidly, especially in the regions of low energy. Glass sample VPCu8 reported the highest values for both parameters. Moreover, glass sample VPCu8 had the lowest exposure buildup factor and energy absorption buildup factor values. Our findings showed that CuO-reinforced vanadate glass composition, namely 46V2O5-46P2O5-8CuO, with a glass density of 2.9235 g/cm3, was reported to have superior gamma ray attenuation properties. These results would be helpful for scientists in determining the most appropriate additive rare earth type, as well as the most appropriate glass composition, to offer shielding characteristics similar to those described above, taking into consideration the criteria for usage and the needs of the community. The results of this research will be useful to the scientific community in evaluating the prospective characteristics of CuO-doped glass systems and related glass compositions. CuO-doped glass systems and associated glass compositions have a wide range of properties.

Optical and gamma-ray shielding effectiveness of a newly fabricated P2O5–CaO–Na2O–K2O–PbO glass system

The glasses of composition of 40 P2O5 - 20 CaO- (30-x) Na2O - 10 K2O – x PbO and (x = 0, 5, 10, 15 and 20 mol%) (coded as PbP1, PbP2, PbP3, PbP4 and PbP5 for x = 0, 5, 10, 15 and 20 mol% respectively) were prepared. The physical properties and the optical properties have been studied and found to be affected due to the incorporation of the PbO. Also, FLUKA code was used for the investigation of the linear attenuation coefficients (LAC) for the PbP glass system and to report the role of Na2O and PbO on the radiation shielding parameters. The simulation was performed between 0.637 and 2.506 MeV. At 0.637 MeV, PbP1's LAC is equal to 0.181 cm−1 and PbP5's LAC is equal to 0.337 cm−1, while at 2.506 MeV, their LAC values are 0.092 cm−1 and 4.538 cm−1, respectively. At any energy, the LAC follows the order of PbP1 < PbP2 < PbP3 < PbP4 < PbP5. These results indicate that PbP5, the glass with the highest PbO content, has the greatest LAC at all tested energies, and thus the best shielding capability. The shielding effectiveness of the PbP5 glasses have been compared to that of the commercial shielding SCHOTT AG RS253, RS253G18, RS323G19, RS360 and RS520 glasses at 0.662 MeV. The PbP5 glass possess better shielding properties compared to the RS253, RS253G18, RS323G19 and RS360 commercial shielding glasses.

A new heavy-mineral doped clay brick for gamma-ray protection purposes

The present work novelty pointed to fabricate new clay bricks doped with heavy minerals to be used in the building materials as a candidate for radiation shielding. The bricks were manufactured as (y)Iron mineral+ (1-y)clay, where y = 0, 0.1, 0.2 and 0.3 fractional weight. The prepared bricks' chemical composition and density were introduced to the MCNP-5 code to assess the prepared bricks' protection capacity. The simulated linear attenuation coefficient (LAC) was confirmed by comparing the simulated results with those calculated by the Phy-X/PSD program. We found that the simulated and calculated LAC were close together. The diff (%) between the MCNP-5 and Phy-X/PSD is in the range ±2% for all the fabricated bricks. The maximum LAC values occurred at 0.015 MeV, varied between 21.540 and 39.553 cm−1 for bricks N0 and N30. The lowest LAC achieved at 15 MeV varied between 0.068 and 0.090 cm−1. Bricks without heavy mineral addition have the lowest LAC values at all energies, ranging from 21.540 cm−1 to 0.068 cm−1, while bricks with 30 wt% heavy minerals have the highest LAC. The half-value layer (HVL) values decreased gradually with increasing the mineral ratio in the fabricated bricks. The thinner brick HVL achieved for the sample N 30 with 30 wt % heavy mineral, growing from 0.017 to 7.675 cm. The effective atomic number (Zeff) was reported, and we found that the minimum Zeff values equal to 14.006, 14.865, 15.705, and 16.394 for bricks N 0, N 10, N 20, N 30, respectively.

Bi2O3 reinforced B2O3 + Sb2O3 + Li2O: composition, physical, linear optical characteristics, and photon attenuation capacity

Role of Bi2O3 on the structure, physical, linear optical characteristics, and radiation protection capacity of antimony borate–lithium with the form (65 − x)B2O3 + 10Sb2O3 + 25Li2O + xBi2O3 x = 0 (BSLB0), 4 (BSLB4), 8 (BSLB8), 12 (BSLB12), 16 (BSLB16), 20 (BSLB20) mol% glass systems was examined. The density was increased from 2.7125 to 3.9454 g cm−3 for BSLB0 and BSLB20 glass samples, respectively. The indirect optical bandgap decreases from 2.63 to 2.45 eV, while the direct optical bandgap decreases from 3.06 to 2.89 eV. Therefore, values of the refractive index (n) were varied from 2.50 to 2.56. Both optical (σoptical) and electrical (σelectrical) conductivities were enhanced with increasing Bi2O3 content in the investigated glasses. The observed trend of linear attenuation coefficient (LAC) values throughout the energy spectrum was followed the sequence: (LAC)BSLB20 > (LAC)BSLB16 > (LAC)BSLB12 > (LAC)BSLB8 > (LAC)BSLB4 > (LAC)BSLB0 with values in the range of 0.052–14.469, 0.062–28.291, 0.070–42.738, 0.082–61.708, 0.091–79.616, and 0.104–102.154 cm−1 for BSLB0–BSLB20 glasses, respectively. At each energy within the energy spectrum, the mean free path (MFP) and half value layer (HVL) of the BSLB-glasses were decreased in the order of increasing Bi2O3 content in the glasses. The effective atomic number (Zeff) value varies from 6.53 to 15.12, 6.76–16.32, 7.02–17.37, 7.29–18.36, 7.58–19.29, and 7.89–20.16 for BSLB0–BSLB20 glasses, respectively. Therefore, BSLB-glasses possess superior photon protection capacity than ordinary (OC) and barite (BC) concretes for photons.

A comprehensive investigation on the role of PbO in the structural and radiation shielding attribute of P2O5–CaO–Na2O–K2O–PbO glass system

This study presents the synthesis, physical, structural and gamma-ray shielding characteristics of 40P2O5–20CaO–(30−x)Na2O−10K2O–xPbO (x = 0, 5, 10, 15, 20 mol%) glasses. The glass samples coded as PbCKNP1, PbCKNP2, PbCKNP3, PbCKNP4, and PbCKNP5 were prepared using the melt quench method. Na2O substitution by PbO influenced the molar volume and mass density of the glasses. Structural analysis of the glasses using the X-ray diffraction (XRD) and Fourier transform infrared (FTIR) spectroscopy confirmed amorphous structure. The photon shielding parameters of the glasses examined via the Monte Carlo simulation code (MCNP-5) revealed that the glasses' shielding ability improved as PbO content increased. The highest simulated linear attenuation coefficient (LAC) achieved at 0.015 MeV increased from 21.46 to 159.07 cm−1 as the PbO concentration increased from 0 and 20 mol%. The LAC for all fabricated glass samples showed an exponential reduction trend with gamma photon energy. Based on the simulated LAC values, calculated mass attenuation coefficient (MAC), half-value layer (HVL), transmission factor (TF), and radiation shielding capacity (RSC), PbCKNP5 possessed the best gamma-ray protection ability among the investigated glasses. Furthermore, the calculated shielding parameters of the PbCKNP glasses showed that they possess a good potential for radiation shielding applications.

On the use of green concrete composite as a nuclear radiation shielding material

In the present study, the samples of sustainable green concrete composites reinforced with hematite were prepared by partially replacing Ordinary Portland Cement (OPC) with flyash. The mechanical and gamma radiation shielding parameters have been measured experimentally for these prepared concrete composites. The experimental measurements were performed by using narrow beam transmission geometry (total scatter acceptance angle (θsc) = 1.78°) with NaI(Tl) spectroscopy in the gamma photon energy range of 59.54 keV–1332 keV. These experimentally measured values of linear attenuation coefficient are further used to calculate the values of half value layer, mass attenuation coefficient, effective atomic number, electron density, exposure build up factor, Klein-Nishina electronic, electron transfer and Compton mass attenuation coefficients. The fast neutron removal cross sections (∑R cm−1) were calculated for the concrete samples under investigations. The experimental values of mass attenuation coefficient have been compared with the results of theoretical values obtained by using winXCOM computer software and FLUKA simulations code. Excellent agreements have been observed between experimental, theoretical and simulation results.

Physical, structural, and gamma ray shielding studies on novel (35+x) PbO-5TeO2-20Bi2O3-(20-x) MgO-20B2O3 glasses

The primary aim of this investigation is to synthesize a novel glass system with a composition (35+x) PbO-5TeO2-20Bi2O3-(20-x) MgO-20B2O3 (where x=0, 5, 10, 15, and 20 mol%) by melt quenching method. The confirmation of the amorphous behavior and the presence of the various vibration modes and stretching modes have been analyzed using the XRD and FTIR techniques, respectively. The radiation shielding parameters of these glasses were reported using MCNP5 simulation. The effects of PbO on the MCNP5 parameters were investigated in detail. The mass attenuation coefficient (MAC) was simulated via MCNP5 code, and it was found that the MAC values from MCNP5 all follow the same trend as the XCOM data. The similarity means that the two simulations strongly agree with each other. The linear attenuation coefficient (LAC) was calculated for all the glasses. The glass sample with 55 mol% of the PbO has the greatest LAC at any energy, such as 0.317 at 10 MeV, the lowest investigated energy. From the LAC values, other parameters such as transmission factor (TF), lead equivalent thickness (d lead), and half-value layer (HVL) were reported. The results for the TF of the glasses revealed that the glass systems become more effective as their thickness increases. Glass sample with 35 mol % of the PbO recorded the highest TF at all energies due to its lack of PbO content, such as 15.533% for a thickness of 1 cm and 6.122% for 1.5-cm thickness at 0.3 MeV. The radiation protection efficiency (RPE) was also determined, and we found that the glasses with the greater PbO content and least MgO content have the highest RPE. Therefore, based on the RPE values, glasses with the greater PbO are the most effective radiation shield from the investigated glasses.

Recycling of steel slag aggregates for the development of high density concrete: Alternative & environment-friendly radiation shielding composite

The present study aims in developing high density radiation shielding composite using induction furnace (IF) steel slag as an aggregate (coarse/fine) in concrete. IF steel slag is incorporated in concrete specimens (Mix a - 0% of slag, Mix b - 40% of slag as coarse aggregate, Mix c - 40% of slag as coarse aggregate and 100% as fine aggregate) of size 150 × 150 × 50 mm were fabricated. The presence of various iron (Fe) phases such as hematite, iscorite and almandine in IF steel slag composite were confirmed by XRD analysis. Presently, these types of materials are obtained from natural resources are in use for gamma radiation shielding. Density and compressive strength were studied, further concrete blocks were subjected to irradiation using gamma radiation sources such as 137Cs (0.662 MeV) and 60Co (1.17 and 1.33 MeV). Concrete specimen morphologies and structural changes of before and after irradiation have been studied using SEM and XRD analysis. The results show that replacement of 40% as coarse aggregate and 100% as fine aggregate of slag in concrete increases the density and compressive strength of conventional concrete from 2.38 g cm−3 to 2.85 g cm−3 and 27.20 N mm−2 to 29.38 N mm−2 respectively. Gamma Attenuation Factor (GAF), Linear Attenuation Co-efficient (LAC) and Half Value Layer (HVL) are better than the conventional concrete. Mix c can be a cost-effective alternate composite for radiation shielding studies and can reduce the exploitation of natural resources.

Synthesis and characterization of lead oxide nanostructures for radiation attenuation application

In this study, lead oxide nanostructures (PbO NSs) were synthesized using chemical bath deposition method (CBD). The physical vapor deposition (PVD) technique used to deposit lead oxide seed-layer on the glass substrates. The effects of different deposition time on the morphology, structural and optical properties of lead oxide NSs were studied. Also, the radiation attention coefficient was measured based on synthesized lead oxide NSs with different deposition times. It was observed the alteration of growth time from 5 min to 20 min leads to significant change in morphology from nanofiber like lead oxide structure to the nanoflower like PbO structure. The XRD results, displayed the lead oxide NSs were indexed as Pb3O4 polycrystalline tetragonal phase. Also, the crystal size was in the range of (15.37–85.68) nm, and the growth rate was gradually decreased from 1.9 nm/min to 0.4 nm/min with deposition time from 5 min to 20 min. The synthesized PbO NSs have high transmittance (~80%) in the visible spectrum and low transmittance in the UV region. The energy band gap (Eg) values of the PbO NSs were changed from (2.20–2.36) eV with increasing growth time up to 20 min. The fabricated PbO NSs exhibited a significant performance in radiation shielding. The average radiation attenuation was changed from (14.592–48.642) count/sec as the deposition time increased from 5 min to 20 min. The higher rate of radiation attenuation for PbO NSs was observed at 10 min of deposition time and it was about 14.592 count/sec. The linear attenuation coefficient and half value layer were altered in the range of (226.132 m-1 -1142 m-1) × 104 and (6.0671–30.646) × 10−8, respectively. Also, the minimum and maximum transmission factor was observed for lead oxide NSs fabricated with 10 min and 20 min respectively. In addition, the maximum radiation protection efficiency was estimated for lead oxide NSs at 10 min and it was about 70%.

Fabrication of TeO2-doped strontium borate glasses possessing optimum physical, structural, optical and gamma ray shielding properties

Glasses with composition of (60 − x) TeO2 − 10SrO − (30 + x) B2O3 were fabricated by melt quenching method. The structural features have been studied using X-ray diffraction (XRD) and FTIR. The derivative of absorption spectra fitting (DASF) method has been utilized to determine the optical band-gap energy. The measured band-gap energies takes values 3.521, 3.558, 3.581, 3.620 and 3.669 eV for the BSrTe60, BSrTe55, BSrTe50, BSrTe45 and BSrTe40, respectively. The band-gap energies increase with a decrease in the mol% of concentration of TeO2. The transitions involved are found to be indirect transitions. The MCNP-5 simulation code was put to use in estimating gamma photons' mean path length in the material. The lowest linear attenuation coefficient (µ) values lie within the range of 0.162 and 0.107 cm−1 and are detected around 8 MeV. The LAC values decreased linearly with substituting the TeO2 by B2O3 content. The lowest half-value layer (HVL) is found at low energy (around 0.005 cm at 0.015 MeV). The mean free path (MFP) decreases linearly with increasing the TeO2 content and followed the trend: (MFP)BSrTe60 < (MFP) BSrTe55 < (MFP) BSrTe50 < (MFP) BSrTe45 < (MFP) BSrTe40. The MFP of BSrTe60 and BSrTe55 at 0.662 MeV is 2.620 and 2.950 cm, and this is lower than the MFP of some commercial glasses such as RS 253 (MFP = 5.263 cm, RS 253-G18 (MFP = 5.263 cm), RS 323-G19 (MFP = 3.571 cm) and RS 360 (MFP = 3.125 cm) at the same energy.