Mass Attenuation Coefficient Values Research Articles

The Effects of TeO2 on Polarizability, Optical Transmission, and Photon/Neutron Attenuation Properties of Boro-Zinc-Tellurite Glasses

Boro-zinc-tellurite glasses in the chemical composition of xTeO2–(30 − x)Li2O–20ZnO–50B2O3 (x is ranging from 0 to 20 mol% with step of 5) were systematically studied by means of their optical features such as molar polarizability (αm), molar refraction (Rm), optical transmission (T), metallization principle (M), and reflection loss (RL). Moreover, the Monte Carlo method (via FLUKA code) was applied to investigate the photon and neutron attenuation properties by estimating the mass attenuation coefficient (MAC) of the glasses involved. The MAC values were then utilized to assess various photon attenuation parameters such as HVL, EAN, and MFP. Finally, an extended comparison was achieved between the MFP values of the present glasses and those of various commonly used radiation shields. The results showed that the general trend in MAC throughout the energy spectrum was (TL1)MAC < (TL2)MAC < (TL3)MAC < (TL4)MAC < (TL5)MAC. The TeO2 addition (the substitution of Li2O by TeO2) has a notable impact to increase the LAC values indicating to improve the photon attenuation ability of the current glass specimens. The maximum $${\Sigma_{R} }$$ value was around 0.12 cm−1 for TL1 glass specimen. The investigated glasses could be used for various radiation applications as non-toxic and transparent shields against photon and neutron radiations.

Mechanical, structural and nuclear radiation shielding competencies of some tellurite glasses reinforced with molybdenum trioxide

In this study, a group of molybdenum boro-tellurite glass samples and their mechanical parameters and nuclear radiation shielding competencies were investigated. The amorphous structures of molybdenum boro-tellurite glasses were confirmed by XRD patterns. Synergistic positive effect of MoO3 reinforcement on gamma ray attenuation properties and mechanical parameters was investigated. For this aim, and in the energy range 0.015–15 MeV, the mass attenuation coefficients (MAC) had been computed by computational methods. At 0.015 MeV, the MAC values increase from 28.06 to 33.25 (cm2 g−1) as the MoO3 content increases from 0 to 30 mol %, while the half value layer values decrease from 4.84 to 3.88 (cm) at 15 MeV. The longitudinal ultrasonic velocity (VL) and shear ultrasonic velocity (VS), longitudinal modulus (L), shear modulus (S), bulk modulus (K), and Young’s modulus (Y) increase from 3450 to 3637 (m s−1), from 1994 to 2146 (m s−1), from 53.44 to 64.88 (GPa), from 17.86 to 22.58 (GPa), from 29.63 to 34.77 (GPa), and from 44.61 to 55.69 (GPa), respectively. The analysis of the shielding and mechanical indicates best protection of the explored glasses for γ-irradiation. Based on the analysis, the glass 30MoO3-70TeO2 with the maximum MoO3 addition indicated best γ-irradiation protection and mechanical parameters among the explored glasses.

Neutron and photon shielding competences of aluminum open-cell foams filled with different epoxy mixtures: An experimental study

In this study, ten open-cell aluminum foams with 30 mm thickness 2 pores/cm and 10 mm thickness 16 pores/cm pore sizes encoded A1-A5 and B1–B5 respectively were fabricated by filling with different mixtures which have Epoxy(60wt%)-B2O3(20wt%)-CeO2(15wt%)-(BaO, Cr2O3, WO3, Bi2O3, TiO2) (5wt%) chemical compositions. At first, gamma transmission measurements of the manufactured samples were achieved employing an Ultra Ge detector for 30.9, 59.54, 75, 81, 276, 303, 356, 384, and 662 keV photon energies. The foam samples were also irradiated with 6 MV energy X-rays via a linear accelerator (LINAC). The mass attenuation coefficients (MACs) of the samples and further photon protection parameters derived from MAC were computed with the data acquired from those measurements. It was found that the WO3 and B2O3 doped metal foams had the highest MAC values, whereas the lowest MAC values belonged to the TiO2 doped samples. Half Value Layers (HVL) obtained for two different metal foam samples of 30 mm and 10 mm thickness with Bi2O3 doped were found as 0.096cm-2.962 cm and 0.090 cm–2.921 cm, respectively. While the effective atomic numbers (Zeffs) of the WO3 and Bi2O3 added samples were of the highest values, the Energy absorption and Exposure Buildup Factors (EABF and EBF) calculated with Py-MLBUF in the energy range of 0.015–15 MeV were obtained as minimum compared to others. Finally, the shielding potential of the prepared samples against fast neutrons was assessed by performing equivalent dose measurements (EAD) and calculating macroscopic cross section (∑R) values. In A and B series metal foams, it was observed that the ∑R value was the highest in WO3-doped samples and got 0.1691 cm−1 and 0.1785 cm−1 values, respectively. It was also observed that the absorbed dose rates varied between 23% and 46%. It was concluded that B3 and B4 metal foams with thinner and higher pore sizes and doped with heavy oxides (WO3 and Bi2O3) could be used as an alternative shield material.

Investigations on the gamma-ray shielding performance of green concrete using theoretical, experimental and simulation techniques

A newly developed concrete obtained by partially replacing Ordinary Portland Cement (OPC) by Bismuth-Ground Granulated Blast Furnace Slag (Bi-GGBFS) have been analysed for its gamma-ray shielding behaviour (GSB). The experimental measurements were performed by using narrow beam gamma transmission geometry with scintillation detector, NaI(Tl) 2 ʺ × 2 ʺ, MCA, and point isotropic sources 241Am, 137Cs and 60Co. For the measurements of incident and transmitted gamma photon intensities the value of total scatter acceptance angle (θsc) was 2.13°. These experimentally measured values of linear attenuation coefficient are further used to calculate the values of mean free path (mfp), half value layer (HVL), mass attenuation coefficient (MACμm), effective atomic number (Zeff), electron density (Ne),exposure build up factor (EBF), Klein-Nishina electronic (σeKN), electron transfer (σetr), atomic cross-section σaKN and Compton MACs. The experimental values of mass attenuation coefficient (MACμm) have been compared with the results of FLUKA simulations and theoretical values obtained by using WinXCOM computer software. Excellent agreements have been observed between experimental, theoretical and simulation values of MAC. It has been concluded that Bi-GGBFS concrete offers better GSB that other concretes such as ordinary-concrete, diaspore-flyash concrete, and lead fly-ash concrete.

A comparative study on the nuclear shielding properties of BiBr3 and PbSO4 incorporated composites

Detailed investigations on the photon and neutron attenuation properties of various BiBr3 and PbSO4 incorporated polyester composites have been carried out in terms of evaluating their potential use as new radiation shielding materials. Utilizing HPGe detector-based γ-ray spectrometry, the mass attenuation coefficient values of the polyester materials were calculated over a wide photon energy range of 59.5–1408 keV. The experimental results have been compared to those obtained using XCOM software and showed that the measured attenuation coefficient was in good agreement with the theoretical results at all photon energies studied. Moreover, BiBr3(20%) and PbSO4(20%) exhibit the minimum half value layers (5.94 and 6.58 cm at 661 keV) and highest radiation protection efficiencies (69.80 and 69.67% at 59.9 keV), while the neutron removal cross-sections of BiBr3(5%) and PbSO4(5%) samples were higher than the other composites studied.

Measurement of Total Electronic Cross-Section, Total Atomic Cross-Section, Effective Atomic Numbers, Effective Electron Densities and Kerma for Some Br Compounds

The aim of this study is to calculate the experimental and theoretical the mass attenuation coefficient some Br compounds by using transmission method. Also using these values were determined the total electronic section, total atomic section, effective atomic number, effective electron density and Kerma. We performed the calculations of these values in attenuation by using direct excitation experimental geometry. The total attenuation cross sections of some halogene Br compounds were measured in a narrow beam good geometry using a high resolution Si(Li) detector in the energy with γ photons at 59.543 keV from Am-241 annular source. Theoretical mass attenuation coefficient values were computed from the XCOM data programme, based on mixture rule method. This study provide new insight into the literature since the values of effective atomic number, electron density and Kerma for some Br compounds have not been determined before. According to the results shown in mass attenuation coefficient, Zeff and Neff of Br compounds are closely associated with chemical structure. This research were undertaken to explore how Bromine compounds is gamma ray shielding material.

Investigation of gamma-ray attenuation coefficients for solid boronized 304L stainless steel

In this study, mass attenuation coefficient (μ/ρ) and half value layer (HVL) at Eu-152 and Co-60 energies were used in measuring attenuation coefficients of the solid boronized AISI 304L stainless steel at 950 °C for 2, 4, 6 and 8 h. The experimental mass attenuation coefficients, μ/ρ, and HVL for these materials were compared to theoretical values obtained with WinXCOM. At the same time a new boriding agent (Baybora®-1) also developed for solid boriding method was used. The effects of boron layer size on radiation attenuation of boronized composites were evaluated in relation with gamma-ray transmission and the results of the experiments were interpreted. It could be understood that increased of boron layer in AISI 304L causes of increases in the attenuation coefficient values. The measured values agree with the theoretical values. The interaction parameters for selected samples have been computed and provided in the extended energy range 10−3–104 MeV. The shielding properties prepared stainless steel have also been compared with standard concretes as well as with the standard shielding stainless steel. It is found that the prepared stainless steel is the better shielding substitute to the conventional concretes as well as other standard shielding stainless steel. So, submicron size boron layer used composite materials are more convenient than micron size boron used composite materials as radiation shielding materials for nuclear applications.

Radiation shielding characteristics of selected ceramics using the EPICS2017 library

In this paper, the investigation of the Electron-Photon Interaction Cross Sections 2017 (EPICS2017) library on the shielding properties of several ceramics is presented. The EPICS2017 library was used to calculate the mass attenuation coefficients of different ceramic samples. The results from EPICS2017 were compared with values from several experimental and theoretical methods used in characterizing the photon shielding properties. The experimental mass attenuation coefficient values agreed well with the EPICS2017 evaluations, with relative differences ranging from 0.04–6.58%. The mass attenuation coefficient values derived using MCNP5 simulations agreed with EPICS2017 with a reasonable deviation. XCOM values for mass attenuation coefficients strongly agreed with EPICS2017. The obtained results dictate that EPICS2017 can be used to evaluate the MACs for ceramic systems for which no experimental values are available at various energies. From these findings, the EPICS2017 library can be an important alternative for the future photon shielding research and development of ceramic materials.

Monte Carlo gamma transmission model for characterization of multi-gamma shielding parameters of some heavy metal oxide glasses

The applicability of a simple Monte Carlo gamma transmission model was investigated by characterizing the mass attenuation coefficient, mean free path, and half-value layer for six glass sample simulants of the PbO-Li2O-B2O3 system previously prepared by others. The mass attenuation coefficients were calculated and compared with those of XCOM and the available experimental data for twenty gamma energy lines from 0.107 MeV to 7.12 MeV, and good agreement was obtained. The effects of PbO concentration on the simulated values of mass attenuation coefficient, mean free path, and half-value layer, were calculated and compared with available experimental data in the gamma energy range 0.356-1.332 MeV, and good agreement was found. The glass sample with the optimal gamma shielding for all considered gamma energies was the sample with the chemical formula Pb3B4O9. On the one hand, the Monte Carlo results confirm the applicability of the proposed model for performing additional calculations of photon attenuation properties for different glass compositions, and on the other hand, considering the energy range of gamma-ray photons in a reactor during uranium fission, 0.10-10 MeV, the results suggest the use of the studied glass samples as optical shielding windows in nuclear reactors.

Impact of Bi2O3 modifier concentration on barium-zincborate glasses: physical, structural, elastic, and radiation-shielding properties.

A sequence of Bi2O3 varying barium–zincborate (BZX) glasses with the chemical composition (60-x) B2O3-20ZnO-20BaCO3-xBi2O3-0.5Dy2O3 (where x = 0, 5, 10, 15, 20, 25, and 30 in wt%) is fabricated by melt-quenching method. The fabricated samples were examined for the variation in physical, structural, elastic, and radiation-shielding properties with the Bi2O3 concentration. The structural and compositional evaluations are done using XRD and FTIR spectra. The BZX matrixes consist of the trigonal-planar and tetrahedral groups of borates, BiO3 and BiO6 units of Bi2O3, and the non-bridging oxygen in general. The average single-bond strength values substantiate the increasing ionic nature of the BZX glasses. The variation in the density and molar volume of the BZX series discussed in terms of various structural and elastic properties. The glass-coded BZ15 was found to be the best candidate for the sound-resistant applications based on the atomic packing fraction and the acoustic impedance studies. With MCNP5 simulation, the mass attenuation coefficient (MAC) values of all the samples were calculated and compared with a theoretical approach using the XCOM program. As the amount of Bi2O3 increases, the linear attenuation coefficient (LAC) increases with it at all energies. The LAC values varied between 0.2805 and 0.5269 cm−1 for the investigated glasses at 0.81 MeV. BZ30 glass is the more effective shield due to the highest MAC and LAC values.Graphic abstract

Gamma Ray Shielding Characteristics of Borosilicate Glass Containing ZnO from 0.015 to 10 MeV

In this study, the glass system of xSiO2-20B2O3-10Na2O-4MgO-8CaO-3Al2O3-(55-x)ZnO where x= 0, 5, 10, 15, 20 and 25 wt.% were investigated via the WinXCom program. Radiation shielding characteristics of linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL) and mean free path (MFP) parameters of 6 different glass systems were calculated in the energy range of 0.015-10 MeV. Further, a comparison for HVL values between heavy-weight concrete materials &amp; commercial glasses and our findings was carried out. Furthermore, some important glass property calculations and viscosity-temperature curves were calculated with BatchMaker software. According to the WinXCom calculations, it was found out that LAC and MAC values increased while HVL and MFP values decreased with increasing ZnO content. Particularly, 25 wt.% of ZnO (sample-5) addition ensured to obtain by far the best radiation shielding characteristics at higher photon energies. As a result of the comparison, it was strikingly seen that our glass samples have promising results when compared with heavyweight concrete materials and commercial products. Interestingly, sample-5 can compete even with RS323 G18 (33 wt% PbO content) in higher photon energies despite its low-density value. Moreover, it was determined that our glass systems were found to have glass formation ability with satisfactory glass properties according to BatchMaker estimate calculations.

Effect of bismuth and lithium substitution on radiation shielding properties of zinc borate glass system using Phy-X/PSD simulation

The radiation shielding properties of zinc borate glasses with lithium oxide replacing bismuth oxide were investigated using Phy-X/PSD. The glasses have a composition of (25-x)Bi2O3-60B2O3-15ZnO-xLi2O, where x = 5, 10, 15, 20 and 25 mol%, and are coded as S1, S2, S3, S4, and S5 in increasing Li2O content. Phy-X/PSD was used to determine the mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half value layer (HVL), effective atomic number (Zeff), tenth value layer (TVL), and mean free path (MFP) of the investigated glasses. S1 was found to have the greatest MAC and LAC values, 0.415 cm2/g and 1.868 cm−1 at 0.2447 MeV respectively, while S5 had the least, 0.115 cm2/g and 0.301 cm−1 respectively at the same energy. The maximum HVL values was found at 1.46 MeV and are equal to 2.926 cm, 3.427 cm, 3.766 cm, 4.159 cm, and 5.222 cm for S1, S2, S3, S4, and S5 glasses, respectively. The minimum HVL values occurred at the lowest tested energy, 0.2447 MeV, and increased with increasing energy, meaning that the glasses are more effective at lower energies. The Zeff values inversely correlated with the Li2O content in the glasses, following the order of S1 > S2 > S3 > S4 > S5 at all energies. At 0.41 MeV, the Zeff values are equal to 25.15, 21.52, 17.42, 12.75, and 7.35 for S1, S2, S3, S4, and S5 respectively. At all energies, TVL decreased with increasing density; for instance, decreasing from 17.347 cm to 9.718 cm when density increased from 2.613 g/cm3 to 4.503 g/cm3 at 1.458 MeV. The MFP of the zinc borate glasses were compared against other shielding glasses and it was found that the S1 glass outperformed five of the other glasses at 0.2447 MeV and six of the others at 1.458 MeV. The results proved that the S1 glass, the glass with the greatest Bi2O3 content and density, has the greatest potential for radiation shielding applications.

Measurement of Photon Matter Interaction Parameters for some Iodine Compounds

In this study, total atomic cross-section (σta), total moleculer cross-section (σtm) total electronic cross-section (σte), effective atomic number (Zeff), effective electron density (Neff) and Kerma (K) were determined both experimentally and theoretically values for some iodine compounds. Experimental mass attenuation coefficient (µ/ρ) values for some iodine compounds were calculated with the data obtained from the test results. The theoretical mass attenuation coefficient values of these compounds were calculated with the WinXCOM data program. Also, we have performed the measurements for the calculations of experimental values mass attenuation coefficient using direct transmission experimental geometry. The transmission photon intensity of halogene iodine compounds were measured in a narrow beam experiment geometry was used 59.543 keV γ-ray from an 241Am radioactive source. The tranmissions spectra from iodine compounds were recorded with a Si (Li) detector having a resolution of 155 eV FWHM at 5.9 keV (55Fe) and coupled to a 1024 channel analyzer through a spectroscopic amplifier. This study was provided that new insights into the literature since mass attenuation coefficient experimental values of some I compounds have not been determined previously. More research should be done to observe the changes in the chemical structure of iodine compounds with gamma-ray interaction. This study will shed light on further research.

Nuclear radiation shielding competences of barium-reinforced borosilicate glasses

The gamma photon and neutron shielding effectiveness of borosilicate glasses with alumina in the chemical structure 40SiO2.10B2O3.xBaO.(45 − x)CaO.5Al2O3.yZnO.zMgO glasses (20 ≤ x ≤ 40 mol% and y = z = 6 wt%) was evaluated. The investigated glasses were coded as BCBSA-20B (barium oxide (BaO) = 20 mol%) to BCBSA-40B (barium oxide = 40 mol%). The results showed that the mass attenuation coefficient (MAC) increased when barium oxide increased in the samples, and the samples were arranged in order as BCBSA-20B &lt; BCBSA-25B &lt; BCBSA-30B &lt; BCBSA-35B &lt; BCBSA-40B. In terms of MAC values, the BCBSA-40B sample has the lowest values of half-value layer and mean free path but has the highest values of effective atomic number (Z eff). Moreover, the neutron shielding competences of glasses have been determined by way of calculating the removal cross-section for the fast neutrons, Σ R (cm−1), which was the highest for the BCBSA-40B glass (Σ R = 0.0994 cm−1) among the studied samples. In addition, mass stopping power (Ψ) and the projected range (Φ) for proton and alpha particles were also calculated. It was found that the BCBSA-40B sample has the lowest Ψ and Φ among the studied glasses. It can be concluded that the replacement of the calcium oxide (CaO) content with the barium oxide contents enhances the shielding capacity against the charged particles, electromagnetic radiation and the fast neutrons. The finding of recent investigations can be useful for advanced nuclear engineering and protection studies.

The impact of polymer additive for N95 masks on gamma-ray attenuation properties

This article explores the effectiveness of gamma rays attenuation of various N95 respirator samples by analysing several theoretical parameters such as the Effective Atomic Numbers (Zeff), Half Value Layer (HVL), Mean Free Path (MFP), Mass Attenuation Coefficients (MAC), Tenth Value Layer (TVL), Exposure Build Up Factors (EBF) and Energy Absorption Build Up Factors (EABF). For the selected N95 mask samples, the MAC values corresponding to the energy levels between 0.015 and 20 MeV are measured using the WinXCOM software and the MATLAB code. The parameters including Zeff, TVL, HVL, and MFP are computed using the MAC values derived from the WinXCOM program. EBF and EABF are computed in relation to the penetration depth and incident photon energy by using the (G-P) fitting approximation in estimating the photon build-up factor. The findings showed that having the lowest TVL, HVL, and MFP, the N2 sample has the best output in terms of radiation attenuation purposes. In conclusion, the N2 sample which outperforms other samples is the most promising mask sample when it comes to gamma-ray attenuation features.

Determination of Photon Shielding Parameters for Soils in Mangrove Forests

The mass attenuation coefficient (MAC), effective atomic number (Zeff), and effective electron density (Neff) values of soils in mangrove forests across the Philippine islands were investigated. In addition, ENDF/B-VI.8 cross-section data library was used for interpolating Zeff and Neff values. Photon energies considered in this study ranged from 59.5–1332 keV. MAC values were obtained using MCNP5 and PHITS Monte Carlo (MC) simulations and were found to be in good agreement with XCOM and values in literature. Results for Zeff were in good agreement with values obtained using Phy-X/ZeXTRa program. Each shielding parameter was investigated as a function of SiO2 concentrations.

Gamma-ray/neutron shielding capacity and elastic moduli of MnO–K2O–B2O3 glasses co-doped with Er3+ ions

Gamma-ray/neutron shielding capacity and mechanical properties of erbium-doped potassium manganese borate glasses with the chemical form of (1 − x)MnO–29K2O–70B2O3–xEr2O3: x = 0–1 mol% coded as E0–E5 via bond compression model, XCOM software, and PHITS simulations have been investigated. The bulk modulus (KB.C) values increased from 90.19 for E0 glass sample with free Er2O3 to 101.24 GPa for E5 glass sample with Er2O3 = 1 mol%. The Young’s modulus (EB.C) increased from 102.68 GPa to 115.38 GPa, while the longitudinal modulus (LB.C) increased from 142.31 GPa to 159.81 GPa for E0–E5 glasses. Poisson’s ratio (σB.C) decreased from 0.310261 to 0.310065 with the increase of Er3+ ions in the investigated glasses. Hardness of E0–E5 glasses was increased from 4.96 GPa to 5.58 GPa. The mass attenuation coefficient (µ/ρ) values were the highest at the least energy of 0.284 MeV with values of 0.1080, 0.1096, 0.1113, 0.1129, 0.1145, and 0.1161 cm2 g−1 for E0, E1, E2, E3, E4, and E5, respectively. Moreover, radiation protection efficiency (RPE) of the E0–E5 glasses was estimated using PHITS simulation code. The highest RPE was observed for E5 glass with a thickness of 5 cm. Finally, the neutron shielding capacity of E0–E5 glasses was evaluated in terms of the fast neutron removal cross section (FNRCS). The values of FNRCS increased by adding Er2O3 content and a sharp increase was observed at xEr2O3: x = 0.8 mol%. Generally, one can conclude that the E5 glass sample with the highest Er2O3 (1 mol%) concentration is the best sample as radiation shield among all the studied glasses.

Radiological and physical properties of tissue equivalent mammography phantom: Characterization and analysis methods

This article provides methods to fabricate and characterize tissue equivalent properties of mammography phantom. The characterized properties are elemental composition, effective atomic number, electron density, attenuation coefficient and CT number. Polyvinyl alcohol (PVAL), ethanol solution and graphite powder were used to develop samples of breast phantoms. First, the microstructure and elemental composition of the phantom materials were acquired from the field emission scanning electron microscopy (FESEM). FESEM micrography was a good analytical technique to indicate void spaces within the phantom. Next, the effective atomic number and electron density were calculated from the percentage of elemental composition based on the energy dispersive X-ray analysis (EDXA). Mayneord's formula and the Phy-X/ZeXTRa software were used to evaluate the effective atomic number. The calculations show that the effective atomic number ranged from 7.137 to 7.264 and 6.75–7.05 for Mayneord and Phy-X/ZeXTRa approach respectively. The electron density ranged from 3.191–3.209 × 1023/g. These values were found to be in good agreement with water and breast tissue by ICRP and AAPM standards. Then, the mass attenuation coefficients of the PVAL were calculated based on the transmission of low photons by using X-ray fluorescent (XRF) technique at 16.61–25.26 keV. The mass attenuation coefficient values were found to be close to water and breast tissue when results were compared to XCOM values. Finally, CT images were acquired to measure CT numbers, which were found to be near to CT number of breast tissues, −21.40 to 24.13 HU. Based on the ICRP, AAPM, BIRADS and XCOM standards, the study successfully showed methods to fabricate and characterized mammography phantoms.

Wearable and flexible radiation shielding natural rubber composites: Effect of different radiation shielding fillers

Flexible shielding materials based on natural rubber (NR) composites were successfully prepared and developed. The different radiation shielding fillers including barium carbonate (BaCO3), bismuth oxides (Bi2O3) and barium sulfate (BaSO4) were used as X-rays and gamma rays radiation shielding fillers in NR composites. Crosslink density and mechanical properties (i.e., modulus at 100% elongation, tensile strength, % Elongation at break, hardness and specific gravity) were investigated extensively. It was found that NR/Bi2O3 composite gave highest crosslink density, tensile strength, % Elongation at break and specific gravity. It is noted that all types of radiation shielding fillers showed insignificantly difference in term of modulus at 100% elongation and hardness. For the resulting of gamma radiation attenuation properties, it is seen that NR/Bi2O3 composite gave highest mass attenuation coefficient (μm), lead equivalent and lowest half value layer (HVL), inferring that NR/Bi2O3 composite could be better gamma radiation attenuation than those of NR/BaCO3 and NR/BaSO4 composite. For the X-rays radiation attenuation properties in terms of liner attenuation coefficient (μ), half value layer (HVL) and lead equivalent, the results gave good agreement with gamma radiation attenuation properties. In comparison of half value layer between NR/radiation shielding fillers composites and commercial available radiation shielding materials showed that the NR/Bi2O3 composite provided better gamma radiation shielding than those of commercial radiation shielding window, serpentine, hematite serpentine and ordinary concrete. In addition, all NR composite with different shielding fillers exhibited greater X-rays radiation shielding than those of commercial and X-rays window with better performance in term of flexibilities, extensibilities and elasticities. NR/Bi2O3 composite is the most suitable choice of preparing a novel flexible radiation shielding materials.

Structural and nuclear shielding qualities of B2O3–PbO–Li2O glass system with different Ag2O substitution ratios

Structural and gamma-ray/neutron radiation protection characteristics of (50-x)B2O3 +40PbO+10Li2O + xAg2O (x = 0, 2.5, 5, 7.5, 10 wt fraction (wt) %) glass system encoded BPLA glasses have been extensively surveyed. The structure of the prepared glasses has been investigated over X-Ray Diffraction (XRD) patterns. With the addition of Ag2O, the glasses' amorphous structures have not deteriorated, and the density and molar volumes of BPLA glasses inversely varied. Mass attenuation coefficients (MAC) for BPLA glasses have been generated enjoying Monte Carlo N-Particle- Extended (MCNPX) simulation code for the broad gamma-ray energy range of 0.015–15 MeV. It has been observed that the MAC values of the BPLA10 glass are higher than the others at all energy levels. Furthermore, while Ag2O concentration in the glass has increased, Half Value Layer (HVLs) Energy Absorption and Exposure Buildup Factors (EABFs, and EBFs) have dropped off for photon energies which are important for shielding applications. It has been noticed from these results that owning higher equivalent atomic number (Zeq) values, BPLA10 can be employed effectively for gamma-ray attenuation. Lastly, the results found for fast neutron removal cross-sections (∑R) have shown that the Ag2O additive grew the density and ∑R values of the glasses. As with photon shielding, it is observed that BPLA10 glass can be more preferable in terms of neutron retention according to other glasses. One can conclude that Ag2O enhances the shielding capacity of the glass system studied and BPLA10 glass can be considered as a good material for gamma-rays/fast neutrons shielding.