EABF Values Research Articles

PVC doped with BiNi0.1Fe0.9O3 nano-sized perovskites: Preparation, physical, dielectric properties as well as γ-ray absorption and buildup factors

In this work, multiferroic BiNi0.1Fe0.9O3 nanoparticles (NPs) has been fabricated by Sol-gel process, then six nanocomposities (NCs) sheets of PVC/x (BiNi0.1Fe0.9O3): x = 0.0, 0.5, 1.0, 3.0, 5.0, and 10.0 wt% were produced by means of the solution casting process. The produced sheets coded as pure PVC, PVC/0.5(BiNiFeO3), PVC/1.0(BiNiFeO3), PVC/3.0(BiNiFeO3), PVC/5.0(BiNiFeO3), and PVC/10.0(BiNiFeO3). X-ray diffraction (XRD), physical, dielectric properties, and γ-ray attenuation capacity have been investigated. The dielectric properties of the investigated NCs sheets were tested at 1 V with a range of frequencies from 50 Hz to 5 MHz. The Phy-X/PSD software used to calculate γ-ray shielding parameters. The density (ρ) of the prepared NCs sheets increased from 1.4051 ± 0.0001 g/cm3 to 3.2650 ± 0.0001 g/cm3. Up to 0.5 wt%, the actual part of permittivity decreased as the concentration of BiNiFeO3 NPs filler increased, but then increased as filler concentration raised. With an increase in applied field frequency, all prepared NCs sheets exhibited an increase in Ac conductivity. The sample coded as PVC/10.0(BiNiFeO3) possessed the highest values of mass-(MAC) and linear-(LAC) absorption coefficients. The half-value-layers (HVLs) decreased as the BiNiFeO3 NPs content increased in the samples. Correspondingly, (HVL)PVC/10.0(BiNiFeO3) < (HVL)PVC/5.0(BiNiFeO3) < (HVL)PVC/3.0(BiNiFeO3) < (HVL)PVC/1.0(BiNiFeO3) < (HVL)PVC/0.5(BiNiFeO3) < (HVL)Pure PVC. The effective atomic number (Zeff) has the same trend of MAC and LAC for all investigated sheets. PVC/10.0(BiNiFeO3) sheet possessed the lowest EBF and EABF values among all investigated sheets under study. Results showed that the investigated samples can be used as shields for γ-ray.

Nuclear shielding characteristics of newly developed composite metal foams: Role of CeO2 addition and foam type

In present study, new composite materials which were produced by filling open-cell aluminum foams of different thickness and pore size with various additives were surveyed with respect to photon and fast neutron shielding effectiveness. The metal foam samples were prepared in two different series (A: 30 mm thick with a pore size of 2 pores/cm and B: 10 mm thick with a pore size of 16 pores/cm) according to thickness and pore sizes, and the foams were filled with different mixtures which include Epoxy(60)-B2O3(20)-CaO(20-x)-CeO2(x); (x; 0, 5, 10, 15 and 20 wt%) chemical compositions. Gamma, X-ray and neutron measurements of the produced samples were performed using Ultra-Ge detector, linear accelerator (LINAC) and BF3 neutron detector, respectively. The gamma-transmission measurements were achieved for 30.9, 59.54, 75, 81, 276, 303, 356, 384, and 662 keV photon energies using radioactive sources of 241Am, 137Cs, 133Ba. Linear Attenuation Coefficients (LAC) of the samples were figured out with the data acquired from the measurements and MAC, HVL, Zeff and Ne values were found by way of these values. The MAC, Zeff and Ne values of the samples increased with the rising in the percentage of CeO2 added to the mixture. The energy absorption (EABF) buildup factors of the composite metal foam samples were also determined for the energy range of 0.015–15 MeV at 1–40 mfp penetration depths. It was found that the A5 and B5 samples with 20% CeO2 additive had the least EABF values. Lastly, the shielding capability of the fabricated samples against fast neutrons was specified by executing equivalent dose measurements (EAD) and calculated macroscopic cross section (∑R) values. It was established that the A2 sample had the highest absorption dose rate of 49%. The largest of the theoretically calculated ∑R values belongs to the B5 sample with 20% CeO2 additive. Generally, it was concluded that the samples in the B series, which are thinner and have more pores, have better radiation attenuation capabilities.

Tungsten (VI) oxide reinforced antimony glasses for radiation safety applications: A throughout investigation for determination of radiation shielding properties and transmission factors

We report the functional assessment of tungsten (VI) oxide on gamma-ray attenuation properties of 60Sb2O3-(40-x)NaPO3-xWO3 antimony glasses. The elemental mass-fractions and glass-densities of each glass sample are specified separately for the MCNPX Monte Carlo code. In addition to fundamental gamma absorption properties, Transmission Factors throughout a broad radioisotope energy range were measured. According to findings, holmium (Ho) incorporation into the glass structure resulted in a net increase of 0.3406 g/cm3, whereas cerium (Ce) addition resulted in a net increase of 0.2047 g/cm3. The 40% WO3 reinforced S7 sample was found to have the greatest LAC value, even though seven glass samples exhibited identical behavior. The S2 sample had the lowest HVL values among the glass groups evaluated in this work, computed in the energy range of 0.015–15 MeV. The lowest EBF and EABF values were reported for 40% WO3 reinforced S7 sample with the highest LAC and density values. According to the findings of this research, WO3 will likely make a significant contribution to the gamma ray absorption properties of antimony glasses, which are employed for optical and structural modification. Therefore, it can be concluded that WO3 may be treated monotonically and can be employed successfully in circumstances where gamma-ray absorption characteristics, optical properties, and structural qualities need to be enhanced.

Effects of WO3 reinforcement on the properties of poly(lactic acid) composites for radiation shielding

During this work, efforts have been made to improve the gamma radiation shielding capabilities of poly(lactic acid) (PLA) by including tungsten trioxide (WO3). Simulations and theoretical analyses have been performed on the parameters of radiation shielding. They have been tested across a broad spectrum of energies, from 0.015 to 15 MeV. The values suggest that naturally occurring composites with a high WO3 content may be utilized to improve the gamma shielding properties of PLA/TO (TO ≡ tungsten trioxide) composites for protection applications; such composites can be employed as a covering for the solar cells to prevent damage. The composite samples made of PLA and WO3 were analyzed for a range of photon energies. The results showed rise of considerable proportions in the values of linear attenuation coefficient (μ) and mass attenuation coefficient μm at 0.08 MeV, due to the k-absorption edge of tungsten. In addition, μ and μm for all samples at selected photon energy are increase as the WO3 content increases and decreases with increasing photon energy. The half value layer (T0.5) decreased as the WO3 content increased, with the highest values seen at 15 MeV and the lowest values at 15 keV. The behavior of the mean free path (λ) was identical to T0.5 with regards to the amount of WO3 and the energy of the photon. The T0.5 values of the PLA-W7 were lower than other polymer materials, making it a more efficient material for filtering radiation. The Zeff values of the PLA/TO composite samples were the highest at 0.08 MeV and showed a trend of increasing with energy to 15 MeV. The exposure buildup factor (EBF) and energy absorption buildup factor EABF values were computed using the G-P fitting method and showed that the lowest values were presented for the PLA-W7. An increase in WO3 reinforcement in the PLA sample contributed to the decreased EBF-EABF values. The shielding parameters were determined through calculations done using both Phy-X/PSD and FLUKA, and the results from both are in good agreement with each other. The results of the study demonstrate the effectiveness of PLA-W7 as a material for radiation shielding.

Radiation shielding properties of low-density Ti-based bulk metallic glass composites: a computational study

Bulk metallic glasses (BMGs), a new class of structural and functional materials with unique physical and chemical features like high corrosion resistance, high yield strength, low elastic modulus, and transparency to visible light, indicate they could be potential shield against unwanted radiations. This study presents an attempt to investigate radiation shielding efficiencies of a few titanium (Ti)-based BMGs with low densities of range 4.43–5.15 g/cm3. Different shielding properties viz., attenuation coefficients (μ m and μ), half and tenth value layers (HVL and TVL), mean free path (λ), effective atomic number (Zeff), buildup factors (EBF and EABF), and fast neutron removal cross-section (Σ R ) were evaluated in 0.015 − 15 MeV energy range using Phy-X/PSD software. The interaction of charged particles (i.e., H1 and He+2 ions) with BMG samples was investigated in terms of mass stopping power (MSP) and projected range (PR) by deploying Monte Carlo-based SRIM software. The five-parametric geometric-progression (G-P) fitting method was employed to calculate EBF and EABF, whereas Zeff values were calculated through atomic to electronic cross-section ratio. Further, obtained results were compared with two conventional shielding materials: lead (Pb) and heavy concrete (StMg). We found that among 8 BMGs, sample Ti41.9Zr36.3V12.1Cu6.3Be3.4(S1) with the lowest Ti and highest Zr-composition by mass (41.9% and 36.3%, respectively) exhibited the best gamma-rays, fast neutrons, and H1/He+2 ions shielding characteristics with the highest μ m (0.02–15 MeV), μ (0.015−0.2 MeV), Zeff (0.015–0.06 MeV) and Σ R . These values were higher than that of StMg, but lower than those of Pb. Moreover, S1 exhibited the lowest values of HVL, TVL, and λ in 0.015 − 0.2 MeV region for gamma-rays and also has the lowest MSP and PR values for H1/He+2 ions. However, the lowest EBF and EABF values belonged to BMG S1 in intermediate energy region (0.1−2 MeV) only. But, the sample Ti90Al6V4(S7) was the worst among all BMGs and StMg. Thus, low-density Ti-based BMGs have better performances towards gamma-rays, fast neutrons, and H1/He+2 ions shielding and hence the potential to replace conventional StMgs and toxic Pb-based materials.

Functional assessment of various rare-earth (RE) ion types: An investigation on gamma-ray attenuation properties of GeO2-B2O3-P2O5-ZnO-Tb2O3-RE magneto-optical glasses

We report the functional assessment of various rare-earth (RE) ion types on gamma-ray attenuation properties of GeO2-B2O3-P2O5-ZnO-Tb2O3-RE (where; RE=0; 1 %Ho, 1 %Pr, 1 %Er, 1 %Nd, 1 %Dy, 1 %Ce) magneto-optical glasses. The elemental fractions and densities of each glass sample were specified separately for the MCNPX Monte Carlo code. In addition to fundamental gamma absorption properties, Transmission Factors throughout a broad radioisotope energy range were measured. According to findings, Holmium (Ho) incorporation into the glass structure resulted in a net increase of 0.3406 g/cm3, whereas Cerium (Ce) addition resulted in a net increase of 0.2047 g/cm3. The Ho-doped S2 sample was found to have the greatest LAC value, despite the fact that seven glass samples exhibited identical behavior. The Ho-doped S2 sample had the lowest HVL values among the glass groups evaluated in this work, computed in the energy range of 0.015–15 MeV. The lowest EBF and EABF values were reported for Ho reinforced S2 sample with the highes LAC and density values. For all glass samples, a decrease in TF values was observed depending on the increase in thickness. Among the investigated glasses, Ho and Er reinforced samples (i.e., S2 and S4) showed the minimum TF values at used radioisotope energies. It can be concluded that Ho and Er type rare earth elements may provide the most effective gamma ray absorption properties when they are incorporated into the GeO2-B2O3-P2O5-ZnO-Tb2O3 system.

Multicomponent Ge-As-Te-Pb chalcogenide glasses for radiations shielding applications

Phy-X/PSD online program is used to obtain various radiation shielding indices in a photon energy region located between 0.15 and 15 MeV for Ge25-As10-Te65-x-Pbx (x = 2, 4, 6, 8, 10 at %) chalcogenide glasses. The linear attenuation coefficient LAC, mass attenuation coefficients MAC, effective atomic number Zeff, effective electron density Neff, half-value layer, HVL, tenth value layer TVL, mean free path MEF, energy absorption and exposure buildup factors (EABF, EBF), and fast neutron cross section FNRCS have been introduced. The findings conclude that the LAC and MAC measurements are greater and therefore better than commercial and traditional glasses. Also, it was found that HVL, TVL, and MFP were reduced with the addition of Pb to the tested glasses, which improve the shielding characteristics. Zeff and Neff of the compositions under study were varied as (42.58- 59.75) and (2.36-3.09 x 1023 electrons/g) respectively. A reduction was noticed in EBF and EABF values with the increment of Pb concentration in the investigated glasses at the entire photon energies, at all values of MFP that emphasize the enhancement of shielding properties of these glasses with the addition of lead. FNRCS were found to be changed between 0.87 and 0.095 Cm-1 as Pb content varies from 0.0 to 0.01 respectively that let these glasses

Comparative shielding features for X/Gamma-rays, fast and thermal neutrons of some gadolinium silicoborate glasses

X/Gamma-rays, fast and thermal neutrons shielding properties for eight gadolinium based glasses (labeled as S1:S8) have been investigated at energies between (0.015–15 MeV) using MCNPX code and WinXcom software. The correlation coefficient (R2) was used to assess the degree to which MCNPX results are related to that of WinXcom. For all glass samples, R2 was found close to 1, this infers a perfect degree of correlation between the MCNPX and WinXcom results. Multiple parameters including, mass attenuation coefficient (μ/ρ), half value layer (HVL), mean free path (MFP), effective atomic number (Zeff), electron density (Nel), radiation protection efficiency (RPE), exposure and energy absorption buildup factors (EBF & EABF), specific absorbed fraction of energy (SAFE), kerma relative to air (Ka), macroscopic effective removal cross section (ΣR), and total neutron cross-section of thermal neutron (σt) were determined and compared with that of other frequently used along with recently studied shielding materials. The results show that, as the Gd2O3 content increases, the μ/ρ, Zeff, Nel, RPE, ΣR and σt values increase while HVL, MFP, EBF, EABF, and SAFE values all decrease as follow: the values of MAC ranges from 0.0173 to 1.906 and 0.0281–31.831 cm2 g−1; Zeff varied from 6.027 to 8.836 and 10.497–45.659; HVL varied from 0.152 to 16.750 and 0.005–5.533 cm; Nel varied (from 2.8 to 4.25) x1023 and (2.88–13.96) x1023 (electrons/g) for S1 and S8 respectively. In addition, among all studied glasses, S8 glass sample (with G2dO3 content of 35% mol) provided a fully protection for X-rays (RPE = 100%). Moreover, when compared to other common shielding materials and recently studied glasses (in terms of MFP), the S8 sample was found to have the highest attenuation performance relative to many of these materials. In terms of fast and thermal neutrons, the addition of Gd2O3 had a great effect on increasing the attenuation capability for fast and thermal neutrons as follow: the ΣR and σtotal values were increased from 0.120 to 0.145 cm−1 and from 123.99 to 15,258.73 b for S1 and S8 respectively. In addition, the S8 sample was found to have the highest neutron attenuation performance when compared to other common shielding materials and recently studied glasses. Therefore, S8 sample found to have superior characteristics for radiation and neutron shielding applications. The findings of this study might be highly useful in the future for medicinal and industrial applications.

Gadolinium-tungsten-boron trioxide glasses: A multi-phase research on cross-sections, attenuation coefficients, build-up factors and individual transmission factors using MCNPX

The oxide of the rare earth element gadolinium has the chemical formula Gd2O3. Also known as gadolinium sesquioxide, gadolinium trioxide, and Gadolinia, gadolinium oxide. In this study, various types of fundamental cross-sections, attenuation coefficients, build-up factors and individual transmission factors of high density gadolinium-tungsten-boron trioxide glasses with a chemical composition of (70-x)WO3-xGd2O3 –30B2O3 (where x: 17.5, 20.0, 22.5, 25.0 and 27.5 mol%) are determined using advanced Monte Carlo methods. In addition, gamma transmission factors (TFs) for a range of medical and industrial radioisotopes were calculated using MCNPX (version 2.7.0) Monte Carlo code. The investigated glasses were classified Gd17.5, Gd20.0, Gd22.5, Gd25.0, and Gd27.5 in accordance with xGd2O3. Our findings suggest that the Gd27.5 sample (with highest of Gd2O3 content mol. %) has possessed the maximum linear (µ) and mass (µ/ρ) attenuation coefficients at all gamma-ray energies investigated. The coded glass sample Gd27.5 is achieved the maximum effective atomic number (Zeff) and effective electron density (Neff) owing its superior attenuation properties. In terms of build-up factors, increasing the concentration of xGd2O3 in glasses is decreased the EBF and EABF values for all mean free path values (0.5–40 mfp). At a thickness of 3 cm, the lowest transmission factor (i.e., highest attenuation) was verified for all Gd17.5-Gd27.5 glasses investigated. Consequently, the Gd27.5 sample exhibits superior radiation shielding properties for a large range of photon energy and various medical and industrial radioisotope energies.

Gamma-rays attenuation by mineralized siltstone and dolostone rocks: Monte Carlo simulation, theoretical and experimental evaluations

Radiation shielding performance against gamma rays for four mineralized natural rock samples collected from Um Bogma area, Southwestern Sinai, Egypt was determined by Monte-Carlo simulation, theoretical calculations and confirmed by experimental evaluations. The Monte Carlo simulation was utilized to investigate the shielding capacity of the investigated rock samples in the energy range between 0.015 and 15 MeV. According to the Monte Carlo simulation the best shielding properties were achieved for sample siltstone S22 which contains (Fe–Mn) mineralization and density of 3.85 (g/cm3), where the simulated linear attenuation coefficient decreased from 71.30 cm−1 to 0.09 cm−1, increasing the incident gamma photon energy between 0.015 and 15 MeV. On the other hand, the lowest gamma ray shielding capacity achieved for sample siltstone S24 which rich in iron sulfate, with linear attenuation coefficient decreased from 37.50 cm−1 to 0.05 cm−1, increasing the incident gamma ray energy between 0.015 and 15 MeV, respectively. The gamma ray shielding properties for sample siltstone S22 were examined experimentally to confirm the simulated results. Both of experimental and simulated results are close together, with a difference of ±0.5%. Moreover, the siltstone S22 sample shows a thin half-value layer, high effective and equivalent atomic numbers as well as low EBF and EABF values.

Physical, structural, mechanical and radiation shielding features of waste pharmaceutical glasses doped with Bi2O3

In the present work, by utilizing waste pharmaceutical glass (PG) within the attempt of gaining a value-added product for radiation shielding applications, a new glass system was fabricated with the nominal composition of x Bi2O3 – (100-x)PG (x: 0, 5, 15, 25, and 35 wt%). Conventional melt quenching technique ensured to synthesize five different glass samples, namely Bi0, Bi5, Bi15, Bi25, and Bi35. For understanding the role of Bi2O3 in the PG system, we implemented several characterization analyses, including physical, structural, mechanical, and radiation shielding properties. According to the findings, the density of the glasses varied between 2.5344 and 3.4492 ± 0.001 g.cm−3 for Bi0 to Bi35. On the other hand, the X-ray diffraction (XRD) technique confirmed the non-crystalline structure without any sharp peak existence. The mechanical parameter of the glases decreased with the increasing in Bi2O3 content in the glass composition. Radiation shielding competencies were determined experimentally with gamma transmission measurements with the energy range of 53–3.83 keV. The results were checked with generated outcomes with EpiXS program and MCNPX codes. The Bi35 sample with doped 35 wt% of Bi2O3 owns the lowest of HVL, MFP, EABF, and EBF values and highest MACs and Zeffs, which are desired for a shielding material, among the produced glasses. It is concluded from the outcomes obtained that the addition of Bi2O3 significantly increased the photon shielding ability of PG glasses.

Binary contributions of Dy3+ ions on the mechanical and radiation resistance properties of oxyfluoroborotellurite Dyx-glasses

5CaF2–5BaF2 – 60B2O3–10TeO2 – (20-x)Na2O – xDy2O3: (0.5 ≤ x ≤ 2.5 mol percent) glasses were studied for their physical, mechanical, and gamma radiation resistance. The density of Dy0.5 and Dy2.5 glass samples containing 0.5 and 2.5 mol of Dy2O3 was changed from 2.98 to 3.09 g/cm3, respectively. The estimated values of longitudinal (LB-C) were altered from 171.085 to 165.390 GPa, bulk (KB–C) from 105.100 to 102.680 GPa, Young's (EB-C) from 128.602 to 122.674 GPa, and shear (SB–C) from 49.612 to 47.150 GPa for mechanical characteristics (GPa). The Poisson's ratio (σB-C) was varied between 0.296 and 0.300. The MCNPX code and Py-MLBUF online calculation platform were used to calculate mass attenuation coefficients for all Dyx-glasses. In terms of quantitative values, the acquired results are in good agreement. For all photon energies, the Dy2.5 glass sample exhibits the highest linear (μ) and mass (μm) attenuation coefficients. All analyzed Dyx-glasses exhibit a similar trend in half-value layer (T1/2) and mean free path (MFP), (T1/2, λ)Dy0.5 > (T1/2, λ)Dy1.0 > (T1/2, λ)Dy1.5 > (T1/2, λ)Dy2.0 > (T1/2, λ)Dy2.5. Over the whole gamma-ray energy range, the Dy2.5 sample has the highest effective atomic number (Zeff) values. Across the whole photon energy and penetration depth range, the Dy2.5 has the lowest EBF and EABF values. Because of the maximum contribution of Dysprosium (III)-oxide, the Dy2.5 sample can be deemed superior in terms of gamma-ray shielding qualities.

Lithium-fluoro borotellurite glasses: Nonlinear optical, mechanical characteristics and gamma radiation protection characteristics

This study aimed to investigate a specific lithium-fluoro borotellurite glass system based on (60-x)B2O3-xTeO2-5LiF–5BaO–5Bi2O3 (x = 25, 35, 45, 55, 65, 75, and 85 mol %) composition encoded as BTLBB1- BTLBB7 in terms of their optical, mechanical characteristics, and gamma ray attenuation competencies. The Rmolar possess the values 22.064, 21.546, 21.038, 20.860, 19.998, 18.936, and 20.024 (cm3/mol), while the αmolar possess the values 8.755, 8.550, 8.348, 8.278, 7.936, 7.514, and 7.946 (cm3) for BTLBB1, BTLBB2, BTLBB3, BTLBB4, BTLBB5, BTLBB6, and BTLBB7, respectively. Values of χ(3) were 5.189 × 10−12, 5.150 × 10−12, 4.995 × 10−12, 4.448 × 10−12, 4.624 × 10−12, 4.995 × 10−12, and 5.812 × 10−12 (esu), while values of n2opticalwere 7.821 × 10−11, 7.768 × 10−11, 7.558 × 10−11, 6.813 × 10−11, 7.054 × 10−11, 7.558 × 10−11, and 8.656 × 10−11 for BTLBB1, BTLBB2, BTLBB3, BTLBB4, BTLBB5, BTLBB6, and BTLBB7, respectively. The highest μm values were found for BTLBB7 glass sample (TeO2 = 85 mol%) and obey the trend: (μm)BTLBB7 > (μm) BTLBB6 > (μm) BTLBB5 > (μm) BTLBB4 > (μm) BTLBB3 > (μm) BTLBB2 > (μm) BTLBB1. The T1/2 values were reported as 0.105 cm, 0.092 cm, 0.082 cm, 0.075, 0.067, 0.058 and 0.057 cm for those BTLBB1, BTLBB2, BTLBB3, BTLBB4, BTLBB5, BTLBB6 and BTLBB7 at 0.1 MeV photon energy, respectively. The BTLBB7 sample has the highest overall effective atomic numbers Zeff (55.04), while BTLBB1sample has the lowest values (50.33) at 0.1 MeV photon energy. The BTLBB1sample was reported the maximum EBF and EABF values, while the minimum values were reported for the BTLBB7 sample. The investigated glasses can be used as good candidate for optical fibers, photonic devices, and superior in terms of gamma-photon attenuation capability.

Exploring the FTIR, Optical and Nuclear Radiation Shielding Properties of Samarium-Borate Glass: A Characterization through Experimental and Simulation Methods.

(Tl2O3)30-(Li2O)10-(B2O3)(60−y)-(Sm2O3)y glass system with various Sm2O3 additives (y = 0, 0.2, 0.4, 0.6) was studied in detail. The vibrational modes of the (Tl2O3)30-(Li2O)10-(B2O3)(60−y) network were active at three composition-related IR spectral peaks that differed from those mixed with Samarium (III) oxide at high wavenumber ranges. These glass samples show that their permeability increased with the Samarium (III) oxide content increase. Additionally, the electronic transition between localized states was observed in the samples. The MAC, HVL, and Zeff values for radiation shielding parameters were calculated in the energy range of 0.015–15 MeV using the FLUKA algorithm. In addition, EBF, EABF, and ΣR values were also determined for the prepared glasses. These values indicated that the parameters for shielding (MAC, HVL, Zeff, EBF, EABF, and ΣR) are dependent upon the Samarium (III) oxide content. Furthermore, the addition of Samarium (III) oxide to the examined glass samples greatly reinforced their shielding capacity against gamma photon. The findings of the current study were compared to analyses of the XCOM software, some concretes, and lead. In the experiment, it was found that the SMG0.6 glass sample was the strongest shield.

New shielding ZnO-PbO-TeO2 glasses

The effect of PbO and TeO2 concentration on the photon, fast neutron and charged particles shielding capacity of the ternary ZnO-PbO-TeO2 glass systems with the form [(TeO2)0.7-(PbO)0.3]1−x(ZnO)x: x = 0.15–0.25 mol% (TPZ1-TPZ5) glass system was investigated. For this purpose, the mass attenuation coefficient (MAC=μρ) values of the glasses were produced with MCNPX codes and WinXCOM program in the wide energy range of 0.015–15 MeV. Due to the high PbO and TeO2 contributions, the largest MAC values were obtained for the TPZ5 glass. Then important gamma parameters such as effective atomic number, half value layer, effective electron density, equivalent atomic number, and exposure and energy absorption buildup factors (Zeff, HVL, Nel, Zeq and EBF and EABF) were also calculated for TPZ glasses. While the highest Zeff values were found for TPZ5 glass, changing between 48.43 and 51.01, the lowest HVL, EABF and EBF values were calculated for TPZ5 glass. As can be seen from the removal cross section, mass stopping power, and projected range (ΣR, MSP, and PR) results for TPZ glasses, the TPZ5 glass can also be a good shielding material for fast neutrons and alpha-proton particles. As a result, the hypothesis of the study has been confirmed and we believe that the obtained data from this study will be beneficial for the potential use of Te-based glasses in shielding applications.

Nb2O5-Li2O-Bi2O3-B2O3 novel glassy system: evaluation of optical, mechanical, and gamma shielding parameters

For the Nb2O5-Li2O-Bi2O3-B2O3 glass system, optical, structure, mechanical gamma, and neutron radiation shielding aspects were examined comprehensively. The two probabilities of the bandgaps, direct and indirect transition, were evaluated. The absorbance of the recent glasses was increased as Nb2O5 increased. Moreover, the peak shifted to a longer wavelength as Nb2O5 increased. Our results show a decreasing behavior of both kinds of the bandgap. Adopting XCOM within 0.04–15 MeV, LAC and MAC were evaluated for all samples and calculated MAC values are in excellent compliance with deduced FLUKA code respective MAC outcomes. Zeff, HVL, and MFP values were estimated. MAC, Zeff, HVL, and MFP values depended on glass components and energy. Moreover, using equivalent atomic numbers (Zeq) and the geometric progression fitting procedure, EABF values were calculated up to 40 mfp, within 0.015–15 MeV. Comparatively higher density (4.9454 g/cm3), greater LAC, MAC, Zeff, Zeq, and lower HVL, MFP, EABF values achieved for 10Nb2O5-10Li2O-30Bi2O3-50B2O3 glass indicated it as a better gamma shield. Furthermore, the calculated ΣR shows that the 10Nb2O5-10Li2O-30Bi2O3-50B2O3 sample has commensurately greater ΣR (= 0.1744 cm−1).

Multi-objective optimization strategies for radiation shielding performance of BZBB glasses using Bi2O3: A FLUKA Monte Carlo code calculations

Highly efficient gamma shielding of BZBB glasses with various Bi2O3 concentrations in the xBi2O3-30B2O3-(65-x)ZnO-5BaO, (5 ≤ x ≤ 25 mol%) were evaluated for their radiation shielding properties. The μm results have been evaluated via the NISTXCOM database and simulated via FLUKA code. The simulation values by Monte Carlo code (FLUKA) have been shown to converge and correlate with XCOM values. Shielding properties like HVL, MFP, Zeff, EBF, and EABF values have been computed. The values observed that μm and Zeff increase with increasing Bi2O3. 47.09, 48.91, 50.73, 52.54 and 54.36 (cm2/g) are the μm values for BZBB1, BZBB2, BZBB3, BZBB4 and BZBB5 glasses at 15 keV. Also, the μm values decrease with increasing photon energy for all glass samples. Moreover, BZBB5 sample had the lowest HVL, MFP, EBF, and EABF values. That indicates to the addition of Bi2O3 improves the radiation shielding properties of BZBB glasses. The obtained results were compared with the most commonly shielding materials such as lead and concretes. It was concluded that the improved BZBB glasses with the addition of Bi2O3 showed excellent shielding properties comparing with shielding materials. These results could be highly beneficial for fields such as medical treatment facilities.

FTIR, structural and radiation attenuation properties of amalgam dental composites for medical applications

Dental amalgam is one of the most adapted ceramic material which is used in dentistry. On the other hand, they are candidate materials for ionizing radiation exposure during the diagnostic imaging and therapeutic applications. This study is focused on determination of some vital material and physical parameters of dental amalgam composites. The elementary test of the dental amalgam composites have performed using SEM and EDS. On the other hand some significant photon interaction parameters such as mass attenuation coefficients (μ/ρ), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Zeff) and effective electron density (Nel), energy build up factor (EBF), exposure the factor (EABF) of investigated materials have been determined. The last composition encoded DA5 has obtained with a smooth surface with some small agglomeration. The results showed that DA5 sample has the smallest EABF and EBF values, while DA1 and DA2 own the largest ones. This means that the DA5 sample is more effective than other samples in terms of absorbing gamma radiation.

Optical, structural and nuclear radiation security properties of newly fabricated V2O5-SrO-PbO glass system

In this work, strontium vanadate glasses with the nominal composition (V2O5)60+ (SrO)40-x+(PbO)x (where, x = 0, 5, 10, 20, 30 and 40) were fabricated and their optical, structural, physical and nuclear radiation shielding qualities were examined. Amorphous structures of the vanadate glasses were demonstrated by XRD analysis. With the insertion of PbO into the glasses, the density of the glasses was raised from 3.455 to 4.581 g/cm3, while molar volumes were reduced from 43.57 to 43.27 cm3/mol. It was found that as the addition of PbO is enhanced, the optical band gap energy is declined in the range of 3.96–3.55 eV. The UV- absorption spectra of the strontium vanadate glasses containing PbO were recorded in the wavelength range 200–1100 nm. The refractive indices of the VSP glasses proved that the proposed glass system can be considered as promising materials for photoelectronic and optical filter devices. Finally, nuclear radiation shielding attributes of strontium vanadate glasses with lead oxide additive were determined for gamma photons and fast neutrons. The mass attenuation coefficients (μ/ρ) were obtained working WinXCOM data. With PbO content progressive rising from 0 to 40 wt%, the μ/ρ values were increased. Then other related parameters such as HVL, Zeq, EABF and EBF for gamma-ray shielding were found. With PbO added content instead of SrO, the Zeq values increased while HVL, EBF, and EABF values reduced. In addition, since the addition of PbO was enhanced the density, the capacity of VSP glasses to retain fast neutrons was also increased.

Bioactive glasses with TiO2 additive: Behavior characterization against nuclear radiation and determination of buildup factors

This paper studies the radiation attenuation properties and build up (EBF and EABF) factors of different types of bioactive glasses in the 0.015–15 MeV photon energy range. EBF and EABF values of investigated bioactive glasses are determined by using the G-P fitting method. Moreover, effective removal cross-section values, alpha/proton mass stopping power (MSP), and alpha/proton projected range values (PR) are determined for fast neutrons and charged particles. The investigation indicates that TiO2 additive in the bioactive glasses causes considerable variations in the attenuation properties of bioactive glasses. The results show that the BT2.5 bioactive glass sample has highest attenuation performance among the samples.