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This study ailm was to fabricate and investigate the gamma photon shielding efficiency of antimony (Sb) doped polymer resin composites. The orthophthalic unsaturated polyester resin (C16O7H14) and antimony powder have been used as matrix and filler material, respectively. Gamma radiation shielding capacities of the polymer resin composites doped with 325 mesh sized-antimony particles from 5 to 20 wt% have been investigated. Experimental measurements of the samples have been obtained using an HPGe detector equipped with gamma spectrometer by 241 Am, 133 Ba, 57 Co, 22 Na, 137 Cs, 152 Eu, 54 Mn and 60 Co radioactive point sources varying from 59.5 to 1408.0 keV energies. To explore the gamma-ray attenuation features, linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff), the radiation protection efficiency (RPE) were evaluated. According to the obtained results, it was found that Sb(20%) showed the superior radiation shielding capacity than the other samples. The measured data have been compared with those of WinXCOM, and they were found to be in a good agreement with each other.

WOS:000745913200001 Advanced radiation applications have been widely used and extended to many fields. As a result of this fact, choosing an appropriate shielding material based on the radiation application has become vital. In this regard, the integration of elements into polymer composites has been investigated and contributed to the quantity and quality of radiation shielding materials. This study reports photon attenuation parameters and electromagnetic shielding effectiveness of a novel polymer composite prepared with a matrix reinforced with three different proportions (5, 10, and 15 wt%) of niobium content. Addition of Nb dopant improves both photon attenuation and electromagnetic shielding effectiveness for the investigated composites. Therefore, Nb(15%) polymer composite with highest concentration has been found to be the best absorber for ionizing and non-ionizing radiations. Consequently, the performed analyzes provide evidences that the prepared Nb-reinforced polymer composite could be effectively used as photon radiation attenuator and electromagnetic shielding material.

The present study is extremely associated with the evaluation of cathode ray tube (CRT) waste which is a growing hazardous waste management and disposal issue. The Er-added recycled glasses derived from CRT have been successfully fabricated as a component for Na2O–Al2O3–SiO2–K2O–CaO–SrO–BaO–PbO–Fe2O3–TiO2–Er2O3 glass systems. The waste cathode ray tube panel glass (WPG) series were obtained by inserting the Er2O3 in substitution for CRT in the amounts of 0, 1, 3 and 5 mol%. The synthesized WPG series were then subjected to numerous characterization analysis. One can firmly report that the insertion ratio from 0 to 5 mol% in Er2O3 increased the glass density from 2.9216 to 2.9763 g/cm3. Further, there exists no crystalline formation with the addition of Er2O3, instead, an amorphous nature in all WPG series emerges. Microstructural images captured by the SEM technique also confirm the non-crystallinity of the fabricated samples. Energy dispersive spectroscopy (EDS) in SEM, besides, paved the way for revealing the elemental mapping of the WPG series. From the perspective of radiation shielding competencies, nuclear shielding features have been evaluated in terms of μm and related attenuation parameters at several photon energies of 276.4–1332.5 keV by utilizing narrow beam transmission methods. The experimental data have been also confirmed to those of theoretical results by WinXCom software. The HVL results revealed superior photon radiation shielding performances for recycled WPG glasses in comparison to various concretes. In addition, exposure buildup factor (EBF) values estimated utilizing the G-P fitting approach would be useful to design or develop the synthesized glass systems for shielding applications. Furthermore, the macroscopic effective removal cross-sections for fast neutron (ΣR) have been estimated. In conclusion, the findings clearly demonstrated that Er-incorporated CRT glasses can effectively be implemented in radiation shielding applications instead of Pb having toxic effects.

In the present investigation, mass attenuation coefficients ( μ m ) and some related nuclear shielding quantities of various granite samples have been computed at several photon energies of 0.356, ...

Different types of photon shielding parameters such as total mass attenuation coefficient (μ/ρ), linear attenuation coefficients (μ), half value layers (HVL), mean free paths (MFP), effective atomic numbers (ZEff), energy absorption build-up factors (EABF), exposure build-up factors (EBF) and kerma relative to air were investigated for the fabricated Cu–Ag based alloys. The considered parameters were measured through gamma spectrometer equipped with HPGe detector in order to obtain the experimental attenuation coefficients and other related parameters at various photon energy in the energy range 59.5–1332.5 keV. The measured μ/ρ values were confirmed with WinXCOM database results. FLUKA and GEANT4 simulation codes were used to examine the compatibility of the experimental and WinXCOM database results with these simulation codes. The exposure buildup factors of the alloy samples were estimated with help of Geometric Progression fitting formula over photon energy 0.015–15 MeV up to 40 mfp penetration depth. The results revealed that the exhibited effectiveness of Cu0.2Ag0.8 alloys against high energetic photon radiations had a good performance than that of alternative absorbers such conventional concretes, glasses and some alloys. The results of the present survey can be quite useful for possible applications of such materials, especially in nuclear laboratory and reactor core design for preference of effective photon shielding materials.

This study focused on investigation of gamma photon and neutron shielding features of MgO–BaO–B2O3–TeO2–Cr2O3 glass system. The mass attenuation coefficients (MAC) have been calculated at different photon energies between 0.015 MeV and 10 MeV using MCNPX general-purpose of Monte Carlo code. The obtained mass attenuation coefficients have been utilized to evaluate several attenuation parameters such as half value layer (HVL), tenth value layer (TVL), mean free path (MFP) and effective atomic number (Zeff) through these values. Additionally, exposure buildup factor (EBF) values have been calculated using the G-P fitting approach. Moreover, variation of the shielding quantities has compared with commercial shielding glasses and some concretes. Additionally, the values of the macroscopic effective removal cross-section for fast neutron (ΣR) have been determined. The results showed that sample encoded GS4 showed superior photon attenuation properties among the investigated samples while GS1 showed superior neutron attenuation.

The present study focuses on the results on survey of exposure buildup factor, photon and neutron shielding parameters for B, C and D series SiO2–PbO–CdO-Ga2O3 glasses utilizing MCNPX Monte Carlo code. In order to check out the accuracy of MCNPX results, the computational values of mass attenuation coefficients were confirmed with those of XCOM database in relatively photon energy region of 0.020–20 MeV. The relative deviation between MCNPX and XCOM values is below 10% except for 0B and 2B at 0.060 MeV and 0D and 1D at 0.122 MeV. The gamma ray buildup factors for the three extended glass systems were also determined in a wide energy range of 0.02–15 MeV for penetration depths up to 15 mfp. In addition, some related radiation attenuation parameters have been estimated and deduced that among the selected glasses, C-series sample has best photon shielding performance while being B series glasses the superior materials for neutron, alpha and proton shielding. The results showed that C series glass samples among SPCG glasses have clear advantage in weight decrease in terms of shielding the X- and gamma rays in relatively photon energy region of 0.020–20 MeV. It can be concluded that certain types of glasses which include this kind of mixture may be considered an alternative material for radiation shielding practices.

This paper aims to evaluate not only photon and neutron but also proton and alpha shielding effectiveness of barium bismuth borate glasses doped by CeO2. The mass attenuation coefficients (μ/ρ) of these glasses have been computed utilizing MCNPX (2.6.0) code in a wide energy range of 0.02–20 MeV and compared with the results of WinXCOM software. Afterwards, some photon attenuation parameters such as half-value layer, (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Nel), photon transmission factors (TF) and neutron effective removal cross-sections (ΣR) for the cerium oxide substituted barium bismuth borate glasses have been estimated. Using G-P fitting method, exposure buildup factor (EBF) values have been found over the energy range 0.015–15 MeV up to 40 mfp. In addition, Mass stopping power (MSP) and projected range (PR) values have been calculated for proton particles (H1) and alpha particles (He+2). The results exhibit that the density of the glass can be related to the photon and neutron shielding. A10 glass has the highest ΣR values whereas the lowest TF values in gamma and neutron radiation have been observed for A1 sample. A1 and U glasses possess the highest values of Zeff as well as the smallest values of EBF. It can be concluded that A1 and A10 glasses are alternative materials with terms of photon and neutron attenuation, respectively.

In this research, the radiation shielding parameters for two glass systems with composition of 20MgO-(20-x)Al2O3-57SiO2-3B2O3-xCr2O3 (x = 0, 0.1, 0.25, 0.5 and 1 mol%) and Na2O-Al2O3 SiO2 glasses were studied. For this purpose, a scintillation detector namely 3 × 3 inch NaI(Tl) has been designed for detection of photons through MCNPX simulation code. Thus, the mass attenuation coefficients (μ/ρ) and some other gamma shielding quantities were calculated. The estimated MCNPX data of all the glasses were compared and approved with those of WinXCOM program. The gamma ray buildup factors for the two glass systems were also determined in a wide energy range of 0.02–15 MeV for penetration depths up to 15 mfp. The results revealed that the mass attenuation coefficients for the glass samples in the first glass system are higher than those in the glasses in the second system and thus the glasses coded as MASBC have more ability in reducing radiation than NAS glasses. Among the selected glasses, C4 has the largest values of μρ and lowest half value layer, and therefore this glass sample has better shielding features than other samples. Besides, 3—1 glass sample has the lowest values; therefore this sample has the least ability to block and reduce the incoming gamma radiation. The results also showed that the effective atomic number (Zeff) of the glasses in the first composition increased with increasing the content of Cr2O3, and Zeff in the second glass system (i.e. NAS) increased with increasing the Al2O3 content. The values of mass removal cross section for neutron (ΣR) vary between 0.09112 and 0.09163 and 0.08415–0.08710 for the first and second glass system respectively. The obtained results from the present investigation can be useful to understanding of influence of Cr2O3 and Al2O3 additive on nuclear radiation shielding properties of tellurite MgO-Al2O3-SiO2-B2O3 and Na2O-Al2O3-SiO2 glasses.

A new series of Sm3+ doped Telluroborate glasses with varying TeO2 content have been prepared following the melt quenching technique. The physical properties like density, refractive index, average molecular weight, molar volume, optical dielectric constant, and metallization criterion were calculated. Structural properties like boron-boron separation ( ), molar volume of oxygen (Vo), oxygen packing density (OPD), average coordination number (m), bond density (nb), Poisson ratio (µcal), optical electronegativity (χopt), basicity (Λth), two photon absorption (TPA) coefficient (β), ionic character (Ic), and covalent character (Cc) were calculated. In addition to that, optical bandgap and urbach energy (ΔE) values of the titled glasses have been calculated from Tauc's plot using the absorption spectra. It is observed that boron-boron separation ( ) and OPD increases with the decrease in molar volume of oxygen (Vo). Also, the increasing density and refractive index values with the progressive decrease of molar volume with increasing TeO2 content implies the formation of bridging oxygen (BO) along with nonbridging oxygen (NBO), which is later proved by the Poisson ratio values and basicity values. Further, ionic nature of the Sm3+ doped telluroborate glasses are identified from the measured optical basicity (Λth), covalent, and ionic characteristic factors. The observed variations in the optical electronegativity, basicity, metallization criterion, and optical bandgap energy (Eg) values have been discussed in terms of the structural changes that take place due to the addition of TeO2 into the B2O3 network. The gamma photon shielding properties for the prepared samples were studied using MCNPX code in the energy range of 0.356–1.33 MeV. The obtained mass attenuation coefficient exhibit an increasing trend as the TeO2 content vary from 0 to 40 mol%, especially at the energy 0.356 MeV. Of all the glasses, 4TBS glass sample shows lowest half-value layer value. The study confirms that the replacement of B2O3 by TeO2 enhances the capability of the prepared glass samples to reduce the gamma photons.

Sm3+ doped lithium zinc alumino borate glasses with composition 15ZnF2–12Li2CO3–10BaO–8Al2O3–(55-x) B2O3–xSm2O3 where x=0.1, 0.3, 0.5, 0.7 and 1.1 mol% were prepared by conventional melt quenching technique Their optical, physical, structural, mechanical and luminescence properties are investigated. UV–Vis-NIR absorption spectra showed all possible transitions of samarium ion in this glass matrix. Band gap values for all the glass samples were above 3 eV confirming the insulating nature for the glass. Densities, assessed using the Archimedes rule, were observed to be increasing with increasing samarium concentration. Increase in molar volume with addition of samarium content indicated that the extension of glass network is on account of the increase of number of Non-Bridging Oxygens created by network modifier samarium ions. Scanning Electron Microscopy (SEM) image showed a smooth surface for the synthezied glass. X-Ray Diffraction (XRD) technique was employed to verify the amorphous nature of the glasses. A Makishima and Mackenzie theoretical model gave acceptable approximation of elasticity constants viz. Young's modulus, shear modulus, bulk modulus and Poisson's ratio. The high Vickers hardness values evaluated with mechanical loads of 50, 100, 300, 500, 1000 g force, proved the stability of the glasses. Emission spectra showed a prominent transition 4G5/2→6H7/2 at 598 nm excited with 6H5/2→4P3/2 transition at 401 nm. Luminescence quenching effect was observed beyond 0.3 mol% Sm2O3 addition. The chromaticity coordinates (x, y) clustered in the orange-red region, making these Sm3+ doped lithium zinc alumino borate glasses suitable candidate for applications in LEDs and solid-state lasers.

This study aimed to investigate the gamma-ray and neutron attenuation parameters of cobalt oxide and nickel oxide substituted ten bioactive glasses. The mass attenuation coefficient ( μ / ρ ) for the selected bioactive glasses was calculated using MCNPX code in photon energy range (0.02 MeV - 20 MeV) and the results were compared with the output of WinXcom software. Other vital gamma-ray attenuation parameters such as half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff), and effective electron density (Nel) for the selected bioactive glasses were also calculated for each approach. Gamma-ray and neutron transmission factors as well as neutron effective removal cross-sections of each bioactive glass (ΣR) were also taken into consideration to underline the distinctive parameters. Additionally, exposure buildup factor (EBF) values were found with G-P fitting approach depending on the energy and penetration depths. The results points that, the lowest HVL, TVL and MFP values and the highest neutron effective removal cross-sections (ΣR) values are the characteristics of NiO 4C and CoO-4. The results indicate that the density of the material affects the photon and neutron interaction parameters. While NiO 4C has the lowest TF values for both gamma and neutron radiation, the highest ΣR values are collected from NiO 4C glass material. The gamma and neutron transmission factors (TF) of the studied bioactive glasses support the aforementioned results. The lowest Zeff values were generated for 45S5C and 45S5 ordinary glasses, while CoO-4 and NiO 4C doped glasses are having the highest values of Zeff. EBF values of the glasses were also calculated in the energy range 0.015–15 MeV up to 40 mfp. The smallest EBF values were measured for CoO-4 and NiO 4C glasses. It can be concluded that NiO 4C bioactive glass outperformed compared to other studied samples and is a promising bioactive glass for gamma-ray and neutron attenuation.

Novel optical glasses 10ZnO-5Na2CO3-10Bi2O3-(75-x)B2O3-xEr2O3 with x = (0, 0.1, 0.3, 0.5, 0.7, 1.0) mol%, were synthesized by melt quench technique and characterized through XRD, EDAX, optical and luminescent properties, before and after irradiating them with high energy (1.3 MeV) gamma rays. Moreover, the gamma photons attenuation characterizations for the samples under study were studied. The mass attenuation coefficients for the selected glasses were affected with the addition of Er2O3. Based on the findings from the mass attenuation coefficients, ZNBBEr-5 has better photon attenuation features in comparison with the other samples. Also, arising the Er2O3 content in the glasses, led to increase the effective atomic number. The mean free path for the prepared samples were compared with some shieling glasses. Shielding performance of the present glass samples against gamma radiation reveals pair production is prominent at 1.3 MeV. UV-VIS–NIR absorption edge was red shifted after gamma irradiation indicating the formation of electron/absorption centers in the glass matrix. Thermally stimulated Luminescence (TL) spectroscopy technique showed five electron trap centers at 445K, 491K, 545K, 590K, 620K with acceptable FOM [

Radiation shielding characteristics of different germanate glasses with compositions of Nd doped Bi2O3–SiO2/GeO2–Nd2O3, Sm3+ doped B2O3–GeO2–Gd2O3, Tb3 doped GeO2–B2O3–SiO2–Ga2O3, TeO2–GeO2–Li2O and Na2O–GeO2–P2O5 glasses have been studied using XCOM program at several photon energies between 0.015 and 10 MeV. Dependencies of their photon attenuation properties with the photon energy and the composition have been investigated. The mass attenuation coefficient values and the effective atomic numbers for Nd doped Bi2O3–SiO2/GeO2–Nd2O3glasses are higher than those of the other samples. 69Bi2O3–30GeO2–1.0Nd2O3 has the highest mass attenuation coefficients among the selected samples. The Zeff results revealed that to increase the photon attenuation ability for the germanate glasses, high Z-elements (such as Bi, Te and Tb) in a suitable concentration must be included. The HVL results for the present germanate glasses suggested that the attenuation capacity of the gamma photons increases as the density of the sample increases, hence, the glass sample with high density must be considered for high attenuation ability. Also, the significant influence of modifier contents on the HVL values namely the attenuation ability has been noticed for Tb3 doped GeO2–B2O3–SiO2–Ga2O3 and TeO2–Li2O–GeO2 glasses. Moreover, the values of the mean free path for the selected samples have been compared with those of different radiation shielding glasses and concrete samples.

In this paper, we studied the gamma photon attenuation properties for different germanate glasses systems with composition Sb2O3–GeO2–SiO2–Al2O3, TeO2–WO3–GeO2, GeO2–TeO2/SiO2–PbO–CaO–Tm2O3 and B2O3–GeO2–Gd2O3–Eu2O3–GdF3–BaF2. The mass attenuation coefficients (μ/ρ) for the selected germanate glasses were calculated at different energies (between 0.015 MeV and 15 MeV) using the MCNPX code. The calculated MCNPX μ/ρ values then compared with the WinXCom data to check the accuracy in the results. The results showed that the Sb2O3 replacement by SiO2 causes a decrease in μ/ρ for Sb2O3–GeO2–SiO2–Al2O3 glass system. Also, it is found that for TeO2–WO3–GeO2 glass system, μ/ρ decreases as GeO2 content increases from 1 to 20 mol%. While for GeO2–TeO2/SiO2–PbO–CaO–Tm2O3 glass system, the results revealed that the glass samples contain TeO2 possess higher μ/ρ values than the samples contain SiO2. For the B2O3–GeO2–Gd2O3–Eu2O3–GdF3–BaF2 glasses, we found that the μ/ρ values decrease as BaF2 is increased from 0 to 15 mol%. Moreover, it is found that 50Sb-0Ge for series 1, TWG0 for series 2, 2G4T for series 3 and X = 0 for series 4 glass samples among the studied glasses have the highest effective atomic number values. On the basis of the results achieved, 50Sb-0Ge, TWG0, 2G4T and X = 0 samples have the best radiation shielding characteristics among the selected glasses.

This study focuses on radiation shielding characteristics of Li2O, Al2O3 and ZnO-doped boron phosphate glasses containing PbO and Bi2O3. Mass attenuation coefficient (μ/ρ) values of the glasses have been calculated using MCNPX code at various photon energies ranging from 60 to 120 keV and compared to those of XCOM software. The obtained results exhibited that MCNPX and XCOM are in good agreement at all energies. Some shielding parameters such as effective atomic number (Zeff), effective electron density (Nel), half value layer (HVL), mean free path (MFP) and Photon transmission factors (TF-photon) were determined using the obtained mass attenuation coefficients. Moreover, macroscopic effective removal cross sections (ΣR) and neutron transmission factors (TF-neutron) for fast neutrons have been evaluated. To simulate the attenuation properties of investigated glasses in a diagnostic radiology operation facility (control room), each boron phosphate glass sample was placed in front of a mathematical human head phantom namely SNYDER. For the glasses under examination, average photon flux in the eight detection points, which were located in different points of SNYDER head phantom, was calculated. Among the studied glasses, BPM4 sample has showed superior photon and neutron radiation shielding effectiveness. It can be concluded that boron-doped glasses are superior shielding materials for both gamma ray and neutrons. Keywords: Boron phosphate glasses, MCNPX, Radiation protection, SNYDER

WOS:000460704700016 Glass systems of composition 16XO-3Al(2)O(3)-6CuO-20Na(2)O-55P(2)O(5) (where X = Sr, Ca, Mg and Ba mol%) have been investigated to check its potential utilize as gamma ray shielding material. Different shielding quantifies namely mass attenuation coefficient (mu/rho), effective atomic number (Z(eff)), half value layer (HVL) and mean free path (MFP) have been evaluated using MCNPX code and XCOM program at different photon energies between 0.015 and 10 MeV. The obtained data revealed good agreement between the mu/rho values derived from XCOM and MCNPX code (version 2.6.0). It is found that the mass attenuation coefficients of BaO-doped phosphate glass are higher than those of the other alkaline earth elements-doped glasses, whereas MgO possess the lowest values. This indicates that the BaO-doped phosphate glass is the superior gamma radiation attenuator among the studied glass samples. The gamma shielding performance of the glasses under study has been compared to some commercial glasses and different concrete samples in terms of MFP. Karamanoglu Mehmetbey UniversityKaramanoglu Mehmetbey University [13-M-17]; Universiti Putra Malaysia (UPM) under Inisiatif Putra Muda (IPM); Hashemite University This study was supported by Karamanoglu Mehmetbey University (Project Numbers: 13-M-17) and the financial support from Universiti Putra Malaysia (UPM) under Inisiatif Putra Muda (IPM) are gratefully acknowledged. The Hashemite University is also acknowledged for the generous support.

In an attempt to develop a novel gamma radiation shielding glasses, we prepared borate glasses contains a high concentration of heavy metals like Bi2O3 and MoO3 with the composition of 20MoO3-(80-x)B2O3-xBi2O3, were x varied from 30 to 45 mol% using tradition melt-quenching-annealing method. A structural investigation such as XRD and FTIR were characterized to confirm the amorphous structure of the prepared glasses and prove the availability of all chemicals included in these compositions after the melting process. Furthermore, optical studies on these glasses were investigated to prove the transparency of the fabricated glasses. Attenuation characteristics (mass attenuation coefficients, radiation protection efficiency, and half value layer) of the prepared glasses with respect to gamma photons (in the range of 0.356–1.33 MeV) were investigated. The mass attenuation coefficients and radiation protection efficiency results increased with increasing the Bi2O3 content and this improves the attenuation ability for the prepared samples. The radiation protection efficiency also revealed that the glasses have the maximum capability in attenuation gamma photons at 0.356 MeV. The mean free path with the prepared glasses was compared with some concretes which is reported in the literature and with some commercial glasses to assess their potential for use in gamma radiation shielding products.

Shielding materials are necessary to protect humans from harmful X-rays that are widely used, especially with low cost and efficient materials. As the present utilization method for iron concentrate may harm the environment, cleaner production methods would be useful. In this paper, a cleaner production method was proposed for iron concentrate in the Liaoning province of China to prepare shielding material for X-rays. The theoretical shielding parameter was calculated using the WinXcom program. X-ray shielding effectiveness was measured at 60–250 kVp using an X-ray machine. The results demonstrate that the mass attenuation coefficients of iron concentrate are lower than PbO but higher than the epoxy resin matrix. Photoelectric absorption, coherent scattering, and incoherent scattering are the main methods for shielding X-rays. The shielding percentage increases as the thickness of the prepared shielding composite increases and decreases with the increase in the X-ray tube voltage. The shielding percentage is more than 76% at 60–250 kVp at a composite thickness of 1.5 cm. The effect of the addition of PbO filler to the matrix material was also analyzed. The shielding percentage of the composite increased rapidly with PbO addition but decreased with the increase in the X-ray tube voltages. The effect of the density also demonstrates that the addition of PbO will significantly improve the shielding performance. The shielding percentage of composites with PbO was more than 90％ at 60–250 kVp. Moreover, the shielding effectiveness of all prepared composites was superior to some shielding concretes. Iron concentrate is potentially low cost and efficient alternative filler for X-ray shielding.

In this study, four newly developed chromium ore based new heavy concretes containing different types of minerals (chromium ore, hematite (Fe2O3), titanium oxide (TiO2), limonite (FeO(OH)nH2O), and siderite (FeCO3) and compounds (galena (PbS), chromium oxide (Cr2O3) and manganese oxide (MnO2) were investigated for neutron and gamma shielding effectiveness. It was observed that the developed concretes have strength up to 30 MPa (4351.131 psi) using mechanical stress tests. In addition, temperature resistance tests were carried out and the results were found to be up to desired level. GEANT4 simulation was employed to determine the effective removal cross-section ΣR (cm−1), transmission number mean free path (MFP), and half value layer (HVL) of the concretes. The equivalent dose rate of fast neutron was calculated using Am–Be source and BF3 proportional counter. Gamma-ray shielding properties mass attenuation coefficients, half-value layer, mean free path, and effective atomic number of the concretes were assessed in the energy range between 0.015 and 15 MeV. The obtained results were compared with paraffin, ordinary concretes, and some heavy concretes. Both theoretical and experimental calculations have shown that all new heavy concretes are capable of absorbing high rates of gamma and neutron radiation than reference samples. In particular, the D3 sample has the maximum neutron attenuation dose value, which contains 55% chromium ore. D2 is superior gamma shielding concrete and this contains 60% chromium ore, 10% hematite, 5% TiO2 and 5% PbS. The new developed concretes are found to be alternative shielding material for the nuclear energy applications.

In this study, new glasses were designed and produced that did not consist of toxic lead oxide (PbO). Unlike conventional glass with powdered silicon oxide (SiO2) added [cobalt oxide (CoO), cadmium tungsten oxide (CdWO4), bismuth oxide (Bi2O3), chromium oxide (Cr2O3), and boron oxide (B2O3)], new glass specimens were fabricated via melt-quenching. The total macroscopic cross-sections, mean free path, and transmission number were calculated using GEANT4 Monte Carlo code. The equivalent dose rates were measured for 4.5 MeV fast neutrons. Gamma attenuation experiments were conducted at several energies in a range of 53-383 keV. The experimental and theoretical results were compared with those of construction concrete, paraffin, glasses containing lead, borosilicate, normal window, and soda glasses. The new glass minimized both gamma and neutron radiation leaks that may occur in various fields such as radiation treatment, nuclear power plants, radioactive waste transport and storage, and space and laboratory research., Ataturk University [2015/337, FBA-2017-6312]; Agri Ibrahim Cecen University [MYO.18.001-19.001], This study was supported by the Ataturk University Scientific Research Projects (2015/337, FBA-2017-6312) and Agri Ibrahim Cecen University (grant no. MYO.18.001-19.001).

AGAR, OSMAN/0000-0003-3807-1587 WOS: 000517161800007 The preparation of materials with high attenuation performance is one of the major issues in the radiation shielding applications. This study is based on the investigation of gamma-shielding performances of various polyester composites reinforced with Zn. Utilizing gamma spectrometer based on HPGe detector, the mass attenuation coefficient (mu/rho) of the present composites was measured at various photon energies between 59.5-1408 keV. The obtained experimental data were confirmed with those of MCNPX code as well as XCOM program. It is found that the attenuation coefficient values of the studied composites are in good agreement with the results of other approaches at the investigated energies. The best photon-shielding effectiveness was observed in the composite tagged with Zn (10%). The shielding characteristics of composite enhances with the addition of Zn as filler.

WOS:000454026000007 Natural sepiolite mineral is a naturally occurring clay form belonging to a part of layered silicate. Because of its advantages such as low production cost, light-weight and convenient, it may be selected as an alternative shielding material to others. Radiation shielding performances of some concretes to sepiolite and B4C addictive have been researched reported in a wide energy region of 0.08-1.333 MeV using experimental data, MCNP and XCOM. The simulated data obtained by MCNPX are discussed and compared with the experimental results as well as with the XCOM results. The simulations match the experiments very well except for S3 sample. From the measurement, the maximum gamma-ray attenuation was detected in the concrete specimen with 10% sepiolite (S1) while the minimum attenuation of gamma-ray was noted in the concrete specimen with 30% sepiolite (S3). The addition of sepiolite mineral to concretes may be an alternative option that can be used in several radiation protection applications. Karamanoglu Mehmetbey UniversityKaramanoglu Mehmetbey University [13-M-17]; Universiti Putra Malaysia (UPM) This work was supported by Karamanoglu Mehmetbey University (Project Numbers: 13-M-17) and the financial support from Universiti Putra Malaysia (UPM) under Inisiatif Putra Muda (IPM) are gratefully acknowledged.

Gamma ray attenuation coefficients for various concrete types containing natural sepiolite mineral and B4C have been experimentally investigated at different gamma energies. In order to obtain the gamma rays, the four radioactive point-isotropic sources 133Ba, 137Cs, 60Co and 22Na which energies ranged from 80.9 to 1332.5 keV have been utilized. The measurements have been carried out by using HPGe detector and MCA equipped with a personal computer. The morphological structure and elemental compositions of the concretes have been measured with scanning electron microscope (SEM) and energy-dispersive X-ray (EDX) analyses. Linear attenuation coefficient (μ), mass attenuation coefficient (μ m ), half value layer (HVL) and mean free path (MFP) have been calculated for all concretes. The obtained results have been compared to the other materials such as Pb and Al.

Various highly effective shielding composites with low cost, light weight, and easy processing were fabricated by addition of various amounts of BaZrO3 and Ba2P2O7 to unsaturated polyester resin. The composites were analyzed by Fourier transform IR spectroscopy, scanning electron microscopy, energy-dispersive X-ray analysis, and X-ray diffraction. A high-purity germanium detector–based gamma spectrometer for experimental tests, WinXCom for theoretical calculations, and Geant4 for simulations were used to analyze the high-energy ionizing radiation shielding performances. The shielding results showed that there is good consistency (relative deviations less than 10%) among the three techniques. Addition of BaZrO3 and Ba2P2O7 as a filler in the composite enhances the radiation protection characteristics of the unsaturated polyester, and the composites with 20% BaZrO3 and 20% Ba2P2O7 had the most effective radiation shielding performance. Consequently, these innovative composites as radiation shielding materials are predicted to benefit medical physics and nuclear science applications.

In this study, CdS doped polyester composites were produced at different weight ratios, and the impact of dopant amount on gamma and neutron shielding characteristics of a new composite material were further evaluated: the composite matrix was doped at 5%, 10%, 15% and 20% CdS weight ratios of the prepared composite. Then, the produced polyester materials have been characterized using a scanning electron microscope (SEM) and X-ray diffraction (XRD) patterns. Following the structure characterization, the prepared composites were tested using one gamma spectrometer system based HPGe detector with help of 22Na, 54Mn, 57Co, 60Co, 133Ba, 137Cs, 152Eu and 241Am radioactive point-isotropic sources in order to perform the evaluation in a wide energy range of gamma. The obtained results were compared to the results of Geant4 and WinXCOM simulation codes. On the last step of the presented work, the neutron removal cross sections of produced polyester composites were calculated using partial density of elements and their cross sections, and then, neutron shielding characteristics of the prepared samples were determined with help of Geant4 simulation toolkit. Both tested and simulated results of gamma shielding evaluation showed good agreement, and, for all considered photon energies, mass attenuation coefficient (μ/ρ) values of CdS (20%) were always found to be greater than the μ/ρ values of other samples (5%, 10%, 15%). The results for neutron shielding showed that neutron transmission was decreasing with the increase of CdS in the material. In short, having higher μ/ρ values and lower neutron transmission shows that increasing the amount of CdS in the sample causes the higher radiation shielding property for both gamma and neutron.

In this study, the γ-ray energy-dependent mass and linear attenuation coefficients of various granite and Turkish marble species have been experimentally obtained. Radionuclides (133Ba, 137Cs, 60Co and 22Na) with point geometry were used as γ-ray sources. The absorption capacity of each sample at nine γ-ray energies was measured using a high resolution γ-ray spectrometer equipped with a high purity germanium (HPGe) detector. To obtain the precision of the results (1σ standard deviation of the single value), this procedure was repeated six times for each species of granite and marble, respectively. The energy-dependent mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), the half (HVL) and the tenth value layer (TVL) were calculated following that the MAC and LAC results were compared to the literature values.

In this analytical work, some components (Sr, Ni, Mg, Fe, Zr, Cd, As, Ca, Br, Rb, Mn, I, Zn, Pb, Tl, U and Ba) of soil samples collected in different locations in the surroundings of Karaman, Turkey were determined by photon activation analysis (PAA). This method is based on photonuclear reactions. (γ,n), (γ,2n), (γ,γ') and (γ,p)-type reactions have been observed. The samples were irradiated with bremsstrahlung photons produced by a clinical electron linear accelerator (cLINAC) for up to about 85min. The PAA results were compared with those obtained by X-ray fluorescence (XRF).

In this study, we determine the self attenuation correction factor for lichen samples collected from Erzurum, a city located in the eastern region of Turkey by using gamma-ray spectrometry. The self attenuation correction factor is calculated for 17 lichen samples with densities ranging from 0.683 g/cm3 to 0.886 g/cm3. The transmission method has been used to obtain self-attenuation correction factors. Self attenuation correction factor versus energy fit curve is presented. It is observed that self attenuation correction factor changes with density. At lower energies the self-attenuation correction factor has higher values. At higher energies it has smaller values and tends to become stable.

In this theoretical study, the zinc borate glasses have been modified with lanthanum oxide (La2O3) in a different amount (0, 1, 2, 3 and 4%).The mechanical and shielding properties change after adding of lanthanum oxide in zinc borate glasses depending on the bond compression and Makishima-Mackenzie models. The mass attenuation coefficients have been calculated using the XCOM program and MCNPX simulation code. The results present that La2O3 increment in the glass density modifies the glass mechanical properties and improves the radiation attenuation performances. The variations in the mechanical properties are resulting from the formation of bridging oxygen. The density of the ZnO–B2O3–La2O3 glass system is proportional to La2O3 concentration, which is attributable to the highest molecular weight of La2O3 than those of ZnO and B2O3. Furthermore, the mass attenuation coefficients, effective atomic numbers and effective removal cross-section of the glasses increases as La2O3 contains increase. The half-value layer, tenth value layer, mean free path, buildup factors and mass stopping power of the glasses decrease as La2O3 contain increases. Present results explained the characteristic of ZnO–B2O3–La2O3 glass as a novel nominee for radiation attenuation barrier in the chosen energy zone.

In this study, the gamma radiation shielding features of several environmentally friendly materials were investigated. For this purpose, several attenuation parameters, such as the mass attenuation coefficient ( $$\mu /\rho$$ ), radiation protection efficiency (RPE), and effective atomic number (Zeff) were determined experimentally and compared with numerical data obtained using WinXCom software. In the measurements, the emitted gamma photons were counted by a gamma spectrometer equipped with an HPGe detector using 22Na, 54Mn, 57Co, 60Co, 133Ba, and 137Cs radioactive point sources in the energy region of 81–1333 keV. The obtained results indicate that the $$\mu /\rho$$ and RPE values of the samples decrease with an increase in photon energy. The experimental values are in good agreement with those obtained using WinXCom software. The RPE and Zeff results show that among the studied materials, the NaY0.77Yb0.20Er0.03F4 sample has the best gamma radiation shielding effectiveness.

In this study, a series of 75TeO2-5Li2O-10ZnO-(10-x)Nb2O5-(x)Er2O3 (where x = 0, 0.5, 1.0, 1.5, 2.0 and 2.8 mol%) glasses have been surveyed in terms of photon and neutron shielding characteristics. For this aim, 3 × 3 inch NaI(Tl) detector has been simulated in order to detect photons. Afterwards, the mass attenuation coefficients (μ/ρ) and some shielding quantities such as half-value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff), effective electron density (Nel), equivalent atomic number (Zeq) and exposure build-up factor (EBF) have been calculated. The obtained MCNPX results of all the glasses have been compared and approved with those of XCOM program. Also, their gamma ray buildup factors have been determined in a wide energy range of 0.02–20 MeV for penetration depths up to 15 mfp. Moreover, neutron attenuation abilities of glasses have been evaluated by estimating neutron total effective removal cross section. The results showed that Er2O3 partial replacement of Nb2O5 in 75TeO2-5Li2O-10ZnO-(10- x)Nb2O5-(x)Er2O3 glass system enhances photon and neutron attenuation characteristics. It can be deduced that obtained results from the present investigation can be useful to understanding of influence of Er2O3 on nuclear radiation shielding properties of tellurite glasses. Keywords: Radiation shielding, Er2O3, Tellurite glass, MCNPX code

Bioactive glasses are silicate glasses with sodium, calcium and phosphorus in its composition used to fulfill or support the functions of living tissues in the human body. The superiority of physical and mechanical properties of the bioactive glasses leads to the opportunity to use for radiation protection. From this point of view, radiation absorption parameters of nine bioactive glasses were reported in the present research. The mass attenuation coefficient (μ/ρ) for the selected bioactive glasses was calculated using MCNPX simulation code in the photon energy range 0.02–20 MeV and the results were compared with XCOM data. The values of μ/ρ calculated in two methods were found to support each other. Other vital parameters like half and tenth value layer (HVL and TVL), mean free path (MFP) and effective atomic number (Zeff) for the selected bioactive glasses were also evaluated by utilizing the μ/ρ. ICSW9 glass with more phosphate and sodium contents possess the lowest MFP, HVL and TVL values while has the highest Zeff values among the bioactive glasses under study. To evaluate the neutron protection performance of investigated bioactive glasses, effective removal cross-section values (ΣR) have been determined. The results showed that ICSW9 has also superior neutron attenuation properties. Additionally, exposure buildup factor (EBF) values were found with G-P fitting approach depending on the energy and penetration depths. The bioactive glasses with further equivalent atomic number possesses the minimum value of EBF. Keywords: Bioactive glass, Silicate glasses, Radiation protection, MCNPX

Glasses based on 10ZnO-5Na2CO3-10Bi2O3-(75-x)B2O3-xEr2O3 with x = (0, 0.1, 0.3, 0.5, 0.7, 1.0) mol%, were synthesized by melt quenching technique and characterized through optical and luminescent features, before and after irradiating them with high energy (1.25 MeV) gamma rays. The amorphous nature of the glasses and the presence of various structural groups like BiO6, BO3 and BO4 were confirmed through XRD and FTIR measurements. Optical properties were studied through UV–VIS–NIR absorption spectra. Decrease in band gap values after gamma irradiation confirmed the creation of color centers in the glass matrix. Thermally stimulated Luminescence (TL) and Optically Stimulated Luminescence (OSL) spectroscopy techniques were used to study the trap centers induced after irradiation. The number of peaks and their trapping parameters were assessed using the Computerized Glow Curve Deconvolution (CGCD). The linearity in dose response proves their suitability in usage for dosimeter and shields in radiation zones within the dose. Keywords: Absorption, Erbium, Optically Stimulated Luminescence, Thermoluminescence, Scanning Electron Micrograph, Trap parameters

Tekin, Huseyin Ozan/0000-0002-0997-3488 WOS: 000462778100026 A comprehensive study of photon interaction features has been made for some alloys containing Pd and Ag content to evaluate its possible use as alternative gamma radiations shielding material. The mass attenuation coefficient (mu/rho) of the present alloys was measured at various photon energies between 81 keV-1333 keV utilizing HPGe detector. The measured mu/rho values were compared to those of theoretical and computational (MCNPX code) results. The results exhibited that the mu/rho values of the studied alloys are in the same line with results of WinXCOM software and MCNPX code results at all energies. Moreover, Pd75/Ag25 alloy sample has the maximum radiation protection efficiency (about 53% at 81 keV) and lowest half value layer, which shows that Pd75/Ag25 has superior gamma radiation shielding performance among the other compared alloys. (C) 2018 Korean Nuclear Society, Published by Elsevier Korea LLC.

In the present work, we studied the radiation shielding parameters such as mass attenuation coefficients, effective atomic number, half value layer, mean free path, macroscopic effective removal cross-sections and neutron transmission function for samarium doped lead alumino borate glasses containing barium, lithium and zinc oxides at medical diagnostic energies (between 20 and 150 keV) using MCNPX code. The results showed that the photon attenuation depends on the type of modifier used (i.e. ZnO, BaO or Li2O) and also, upon the energy of the photon. The higher mass attenuation coefficients were found for the glass containing BaO. The results also revealed that the glass containing Li2O has the maximum effective atomic number between 20 and 40 keV. In addition, some important neutron shielding parameters such as macroscopic effective removal cross-sections (ΣR) and neutron transmission function (N/N0) have been calculated for investigated glass samples. Keywords: XCOM, Glasses, MCNPX, Attenuation, Gamma photon, Neutron

WOS:000460704700086 In the present work, some radiation shielding quantifies (mass attenuation coefficients, effective atomic number, effective electron density, half value layer and mean free path) for various BaO-MoO3-P2O5 ternary glass systems have been determined within the 0.015-15 MeV energy range, using WinXCom program. Additionally, the mass attenuation coefficients of all the investigated glasses have been calculated using MCNPX simulation code (version 2.6.0) and compared to those of WinXCom results. Among the studied glasses, BaMoP8 glass sample with MoO3 content of 70% mol is found to have superior gamma-ray shielding characteristics. Moreover, the glasses studied in this paper possess better radiation shielding properties by providing shorter half value layer (HVL) than RS-253 G18 commercial glass and some concrete samples namely ordinary, hematite-serpentine and ilmanite-limonite. UPM [GP-IPM/2016/9484400] Authors would like gratefully acknowledge use of the services and facilities of Universiti Putra Malaysia (UPM), Malaysia where this work was supported by UPM under GP-IPM/2016/9484400 grant.

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.

Polyester is strong and durable material and tends to retain its shape, thus polyester composites have become highly preferred option in high-tech applications. This motivates the usage of polyester composites in the production of radiation shielding materials as well. In present study, gamma ray shielding properties of polyester composite reinforced with different proportions of Cadmium Telluride (5%, 10%, 15% and 20%) have been investigated theoretically and experimentally. The experiments were performed with the use of HPGe detector in a wide range of photon energies varying from 59.5 to 1408.0 keV while XCOM computer program was computed in the same photon energy range to obtain theoretical results and to verify the experimental outcomes. Remarkable radiation protection efficiency was obtained with additive material of Cadmium Telluride, and the radiation protection efficiency was found to be increased with the increase of additive material amount. Negligible discrepancies between experimental and theoretical results were also observed.

This study investigated the radiation shielding capacity of undoped polymer composite and lead (II) chloride (PbCl2)-containing polymer composite samples. The PbCl(2 )and polyester resin were used as filler and base materials, respectively. The PbCl2 was added to the polyester resin from 5 wt% to 20 wt%, and so an undoped polymer composite and four polymer composite samples each with different PbCl(2 )polymer resin ratios were investigated for their radiation attenuation capacity. Experimental data of the samples were taken using an HPGe detector, and Am-241, Ba-133, Co-57, Na-22, Cs-137, (152) Eu, Mn-54 and Co-60 radioactive point sources were used with energies in the range of 59.5-1408.0 keV. The experimental data were compared with both those simulated with FLUKA code and those theoretically calculated in WinXCOM. Mass attenuation coefficients used in estimating the shielding capacity of the samples were in good agreement with those found using FLUKA and WinXCOM. Radiation protection efficiency was improved by 244% especially at 59.5 keV energy by using PbCl2 (20%) polymer composite compared to undoped polymer composite. The sample with the maximum weight percentage of PbCl2, PbCl2 (20%), had the highest attenuation coefficients and lowest absorption thicknesses, and had the best radiation shielding property compared to the other polymer composite samples.

In this work, photon attenuation performances of the selected TeO2–ZnO–Nb2O5–Gd2O3 glasses have been investigated at various energy points using Phy-X/PSD software. Additionally, neutron shielding properties have been estimated. Dependencies of radiation attenuation capacities with the photon energy and the compositions have been evaluated. According to the obtained results, the mass attenuation coefficients and the effective atomic numbers of tellurite glasses doped with Gd2O3 content of 2.5 mol% are higher than rest of the other samples. Moreover, half value layer and mean free path values of the investigated glass samples recommended that the attenuation capabilities of the ionizing photons increase as the densities of samples increase, hence, the glass having high density must be considered for high attenuation effectiveness. The mass attenuation coefficients vary from 4.87426 to 5.25794 cm2/g for Gd2O3 concentrations with 0 (Gd = 0.0) and 2.5 mol% (Gd = 2.5) at 0.06 MeV. The mean free path values at 0.015 MeV lies within the range 0.00407–0.00493 cm, at 0.1 MeV within the range of 0.1256 to 0.1519 cm, while at 15 MeV has the range of 4.634 to 5.281 cm. The obtained results displayed that among the studied glasses, Gd = 2.5 glass sample with Gd2O3 of 2.5 mol% is found to have superior gamma-ray shielding effectiveness due to having both higher μ/ρ and lower mean free path values.

WOS: 000514749500004 The preparation of materials with high attenuation performance is one of the major issues in the radiation shielding applications. This study is based on the investigation of gamma-shielding characteristics of Bismuth (III) Oxychloride (BiClO) doped polymer concretes. In the produced polymer composites, unsaturated polyester, BiClO, methyl ethyl ketone peroxide (MEKP) and cobalt octoate 6% (CO-6) are chosen as resin, filling material, initiators and accelerators, respectively. The radioactive point-isotropic sources Na-22, Mn-54, Co-57, Co-60, Ba-133, (CS)-C-137, (EU)-E-152 and Am-241 with energies varying from 59.5 keV to 1408.0 keV were used and gamma spectrometer based HPGe detector were employed for the investigation. The obtained experimental data were compared with those of FLUKA code results as well as with XCOM results. We found that the attenuation coefficient values of the studied concretes were in good agreement with the results of other approaches at the investigated energies. BiClO (20%), which is the end-point of compositions studied, has the best radiation shielding property among the prepared polyester concretes. The radiation protection performance of unsaturated polyester resin thus improves with the insertion of BiClO as filler.

Recognizing the vast uses of radioactive sources in several sectors such as industry, medicine, agriculture, development of effective radiation shielding material finds great significance. Present work is aimed to explore potential glass based material for neutron and gamma ray shielding applications. In the present study, several borate glasses with composition of (20 + x) Bi2O3–20BaO–10Na2O–10MgO–(40-x) B2O3 (where x = 0, 5, 10, 15 and 20 mol%) were successfully synthesized via melt-quenching method, and evaluated their gamma-ray and neutron shielding features. The densities of the studied glasses are increased with the addition of Bi2O3 content. The non-existence of any sharp peak in X-ray diffraction spectra confirms the amorphous nature of the glasses. Fourier transform infrared spectroscopy gives the necessary information regarding the structure of the glasses. The optical band gap for both direct and indirect transitions decreases from 2.905 to 2.806 eV and 2.661 to 2.536 eV as B2O3 replaced with Bi2O3. Some quantities namely mass attenuation coefficients ( μ / ρ ) , half-value layer (HVL), mean free path (MFP), macroscopic effective removal cross sections (ΣR) and transmission factor (TF) have been studied theoretically and computationally for gamma-ray and neutron shielding characteristics. The correlation coefficient (R2) values between the XCOM and MCNPX results of all the glasses were found to be almost 1. According to our results, Bi40B20 sample with the highest amount of Bi2O3 has the lowest MFP and TF values, and this suggested that the gamma and neutron shielding performances of the Bi2O3-BaO-Na2O-MgO-B2O3 glasses are improved with the addition of Bi2O3 content.

In order to investigate new candidate glasses for gamma shielding application, we synthesized a number of glasses with composition of (50+x)Bi2O3-(30-x)B2O3-10ZnO-5BaO-5Li2O where x = 10, 15 and 20, all in mol%. We used the conventional melt-quenching-annealing technique with melting temperature at 975 °C and 300 °C for 30 min and 5 h, respectively. Density and other important physical properties have been measured and calculated using related methods and formulas. Moreover, X-ray diffraction have been utilized for all samples to explore the structure of these glasses, the XRD profile have been recorded between 10° to 80° for all samples, while the functional groups of the elements evolved in these glasses have been studied using FTIR with the range of 4000–400 cm−1. Additionally, optical absorption for the synthesized glasses have been measured in the range of 200–800 nm to investigate the cut-off wavelength and optical band gap. Besides, the mass attenuation coefficient values of the present glasses have been estimated through WinXCom software as well as MCNPX computer code and the obtained results were used to determine the effective atomic number (Zeff), the half value layer (HVL) and the mean free path (MFP). From the derived results, it was found that S3 is the superior glass sample in terms of shielding performance on account of larger Zeff values and lower MFP/HVL values among the investigated glasses. The present glasses indicate potentiality to be evaluated as shielding absorbers and for an improved shielding effectiveness of the Bi2O3-B2O3-ZnO-BaO-Li2O glasses, a large Bi2O3 concentration would be required.

In the present study, we utilized the melt quenching method to fabricate (30 + x)PbO 10WO3 10Na2O 10MgO–(40-x)B2O3 (where x = 0, 5, 10, 15 and 20 mol %) glasses. The mass attenuation coefficients (μ/ρ) have been measured at four energies using gamma spectrometric system and the measured values were validated by MCNPX code and XCOM software. The variation in the experimental, theoretical and MCNPX μ/ρ values coincided with each other in all energy regions. The linear attenuation coefficient values for the prepared glasses are proportional to the increase of PbO concentration; however reduce with the increasing photon energy. Besides, we found that the addition of PbO to the glasses leads to reduce in HVL values in the photon energy range, which suggested that the addition of PbO in the synthesized glasses enhances property of more photons absorption of the glass samples. The effective atomic number (Zeff) for the prepared glasses was also calculated and then, we discussed the effect of PbO on the Zeff. The Zeff values lie within range of 29.95–42.77, 20.90 to 30.88, 17.99 to 26.46, and 17.74 to 26.07 for 0.356, 0.662, 1.173 and 1.33 MeV, respectively.