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This paper presents the fabrication of glasses with chemical formula [(TeO 2) 0.70 – (ZnO) 0.22 – (PbO) 0.08 ] 1-x (MnO 2) x where x = 0.02, 0.04, 0.06, 0.08 and 0.1 using melt quenching technique. The main objective is to explore the structural, elastic and gamma ray shielding efficiency of the glasses. The study was conducted using density and molar volume measurements, X-ray diffraction analysis, Fourier transform infrared analysis, non-destructive ultrasonic analysis, and theoretical assessment of the glasses' gamma ray shielding efficiency using the Phy-X/PSD software. High density values in the range of 5.611–5.735 gcm−3 and the XRD analysis showed no sharp peak indicating the amorphous nature of the glasses. The FTIR spectra revealed the presence of both TeO 3 and TeO 4 structural units. The values of the elastic moduli microhardness, Debye and softening temperatures, acoustic impedance, diffusion constant, Thermal expansion coefficient and latent heat of melting were studied and discussed among others. Efficiency parameters of radiation shielding such as the coefficients of mass and linear attenuation, effective atomic number, half and tenth value layers, mean free path and effective electron density were calculated theoretically and discussed. Based on the results discussed, the studied MnO 2 doped TeO 2 -PbO-ZnO glasses appeared to be mechanically strong, and thermally stable for radiation shielding applications. Moreso, the glasses appeared to be better in terms of radiation shielding efficiency than commercial concrete materials like serpentine, barite, ferrite, and chromite. • MnO 2 doped TeO 2 – PbO – ZnO glass system were fabricated using melt-quenching technique. • FTIR, XRD, non-destructive ultrasonic analysis/technique, and density & molar volume were used in the measurements and characterization of the studied glasses. • The high-density value in the range of 5.611–5.735 gcm−3 were recorded and Elastic moduli, Softening & Debye's temperatures, thermal expansion coefficient (α p), acoustic impedance (Z), latent heat of melting (ΔH m) and diffusion constant (D i) were studied. • Phy-X/PSD software was used in calculating the radiation shielding parameters such as Linear Attenuation Coefficient (LAC), Mass Attenuation Coefficient (MAC), and others and the results are discussed. • High values of density, elastic moduli, LAC, MAC, and other parameters suggests the glasses possess great potential for radiation shielding application. [ABSTRACT FROM AUTHOR]

This paper presents a comprehensive investigation of borate-based glasses doped with BaO, assessing their physical, structural, optical, and radiation shielding properties through experimental and theoretical analyses. XRD patterns reveal the amorphous nature of the prepared glass samples. Density and molar volume values, and FTIR spectra indicate the impact of BaO concentration on the glass matrix, affecting structural properties. Thermal analysis via TGA/DSC reveals improved thermal properties with the substitution of B 2 O 3 with BaO. UV–visible absorption spectroscopy shows a decrease in energy band gap with rising BaO content, suggesting potential non-bridging oxygen formation. Mass attenuation coefficient (μ m) values exhibit an exponential decay trend with photon energy, influenced by photoelectric absorption, Compton scattering, and pair creation. The glasses prepared had, in general, a better μ m values compared to that of concretes and other glass compositions containing barium oxide. Experimental and theoretical (XCOM) results for mean free path (MFP) and half-value layer (HVL) demonstrate close agreement, validating the accuracy of the experimental data. Both MFP and HVL increase with energy and decrease with BaO addition, emphasizing the potential for these glasses in radiation shielding applications. • Borate based glass samples of the composition (70-x)B 2 O 3 –20Bi 2 O 3 –5ZnO–5WO 3 -xBaO; x = 0, 5, 10, 15 and 20 mol% have been successfully prepared by melt-quenching process. • The addition of BaO in the glass system improves its density, thermal and gamma radiation shielding properties. • The study elucidates structural modifications of borate glasses imparted by the doping of BaO. • Non-toxic and environmentally friendly nature, along with effective shielding behavior, of our prepared glass samples makes it a practical solution for gamma shielding applications. [ABSTRACT FROM AUTHOR]

This paper focuses on the evaluation of the radiation attenuation properties of 15CaF 2 -10CaO-5B 2 O 3 -(65-x)P 2 O 5 -xNiO-5BaO (where 0 ≤ x ≤ 1.0 mol%) bioactive glasses. The radiation attenuation features of these glasses were investigated by determining different factors including mass attenuation coefficient (μ/ρ), exposure and absorption buildup factors (EBF and EABF), neutron removal cross section (NRCS), and effective atomic number (Z eff) for photon, proton, and carbon ion interactions. Geant4 toolkit and Phy-X program were employed for simulations and calculations procedures. The results revealed that NiO content in the studied bioactive glasses has a significant effect on photon interaction and an insignificant effect on the charged particle interactions. The Z eff values of the studied glasses were observed in the range of 18–20 for photon interaction, 10.7–10.9 for proton interaction, and 10.0–10.7 for carbon ion interaction. The NRCS values were 0.087, 0.088, 0.089, 0.090, and 0.091 cm-1 for x = 0, 0.4, 0.6, 0.8 and 1.0 mol%, respectively. The studied bioactive glasses showed a good ability to attenuate gamma radiation at energies of medical applications. [ABSTRACT FROM AUTHOR]

In this paper, the role of TeO 2 in radiation attenuating characteristics of xTeO 2 -10CaF 2 -(60–0.6x) B 2 O 3 -(30–0.4x) CaO glass system with x = 20, 25, 30, 35 and 40 wt% was investigated. The gamma radiation studies were carried out by utilizing Geant4 simulations and the newly developed Phy-X/PSD program. The gamma-shielding characteristics of the present glass samples were examined in terms of mass attenuation coefficient (μ/ρ), and some other related factors such as the effective atomic number (Z eff), and mean free path (MFP). The electron radiation-shielding characteristics were tested by determining the stopping power (ψ e) and CSDA range for each glass specimen. The neutron radiation-shielding characteristics were explored by evaluating the removal cross section (RCS) for the tested glasses. Moreover, the G-P method was employed to investigate the exposure buildup factor (EBF) for photon energies up to 15 MeV. The results showed that the TeO 2 content had a significant influence on the shielding ability of the investigated glasses against gamma and neutron radiations. In contrast, the TeO 2 content had an insignificant influence on the electron radiation-shielding capacity of the glasses involved. Additionally, the nuclear-shielding properties of the studied samples were compared with those of standard nuclear radiation shields. It can be concluded that the present calcium boro-tellurite glasses have a promising future to be used as a shielding material against gamma, electron and neutron radiation, wherein the TeO 2 concentration can be balanced according to the desired application. [ABSTRACT FROM AUTHOR]

In this research paper, we studied the optical and nuclear shielding efficiency of newly developed BGO glasses with the following compositions (in wt%): 32Bi 2 O 3 –68GeO 2 , 42Bi 2 O 3 –58GeO 2 , 47Bi 2 O 3 –53GeO 2 , 52Bi 2 O–48GeO 2 , 62Bi 2 O 3 –38GeO 2. BGO glasses were prepared by traditional melt quenching method. To obtain the band gap values of fabricated BGO glasses, optical absorption spectra were used for evaluation of optical properties. The mass attenuation coefficients (μ/ρ) were achieved for prepared glasses at 0.015–15 MeV photon energies employing MCNPX Monte Carlo code and WinXcom program. Moreover, broad-range of nuclear shielding parameters for gamma ray, neutrons and charged particles such as mass attenuation coefficient, half value layer, effective atomic number, buildup factors, mass stopping powers, projected ranges, fast neutron removal cross sections and damage factors were calculated. The refractive index is calculated from E opt , As Bi 2 O 3 concentration is enhanced, E opt is also increased as well as the optical electronegativity and consequently the refractive index. In addition, the results showed that BIGE5 glass sample with highest Bi 2 O 3 contribution has excellent nuclear radiation shielding ability among the other fabricated glass samples. [ABSTRACT FROM AUTHOR]

The composite materials filled with different metal particles could provide the potential to meet the proper advantages for gamma radiation protection in both medicine and industry. In this paper, a new, fast, simple and low costing synthesis of bismuth powders using aluminum foil is presented as a gamma-shielding alternative to lead and cement base materials. The synthesized powders were characterized by XRD and FE-SEM. Flexible Bi-PMMA composites having 40, 50 and 60 wt% of bismuth were subsequently prepared and their gamma-shielding properties were investigated. The attenuation constants of the composites such as linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), and mean free path (MFP) were then obtained using the relevant measured values at available energies of Am-241, Cs-137 and Co-60 gamma sources. Gamma-shielding properties of the composites (at each gamma energy) were improved with the weight percentage increase of the bismuth powder in the polymer matrix but on the other hand the shielding capability reduced with the increase of the gamma energy. The HVL value for the sample containing 60 wt % of bismuth powder at a gamma energy level of 59.5 keV was found to be 0.072 cm. This HVL value was very close to that of lead, 0.068 cm, at the same energy. Moreover, the developed composites had the following features: easy and rapid fabrication process, nontoxic nature, lightweight, flexible, environment-friendly, and cost-effective. • Synthesis of Bi powder through a new, fast, simple and low-costing method. • Developing of non-toxic, lightweight, and flexible Bi-PMMA composite films. • Shielding properties of the developed composite films against low energy gamma rays. • Capability of Bi-PMMA composites as a radiation shielding substitution for lead. • Appropriate mechanical properties of the developed Bi-PMMA composite films. [ABSTRACT FROM AUTHOR]

Recent developments have produced low energy X ray systems capable of providing a radiation dose to adequate volumes suitable for sterile inset programmes. To support the adoption of these new systems, the performance of the Gafchromic® HD-810 dosimetry system previously used for gamma irradiation needed to be better understood at the lower photon energies. For low energy photons, the optical density of the irradiated Gafchromic HD-810 film dosimeters significantly depends on the material surrounding them. For example, if paper, Mylar® or PVC is used to house the dosimeter during irradiation, the optical density can vary by as much as a factor of three or more for the same dose. This paper is an attempt to elucidate the performance of the Gafchromic HD-810 film dosimeters for such low energy X radiation (~150 keV). Our data show that this behaviour can be explained by the fact that these materials have significantly different photon mass attenuation coefficient. This conclusion was reinforced with mathematical simulation using Monte Carlo modelling. We also show that with the different structure of another Gafchromic film dosimeter (MD-V2-55) this effect is virtually non-existent. An understanding of the behaviour of thin film dosimeters like Gafchromic HD-810 under radiation is crucial for reliable dosimetry. We hope that this work can also provide guidance in the use of other thin film dosimeters at similar low photon energies. [ABSTRACT FROM AUTHOR]

This paper aims to evaluate not only photon and neutron but also proton and alpha shielding effectiveness of barium bismuth borate glasses doped by CeO 2. 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 (Z eff), effective electron density (N el), photon transmission factors (TF) and neutron effective removal cross-sections (Σ R) 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 Σ R 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 Z eff 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. [ABSTRACT FROM AUTHOR]

Radiation interaction parameters are important for exploring the technological relevance of materials in radiation environments. In this research paper, gamma-ray shielding efficacy of GeO 2 +B 2 O 3 +P 2 O 5 +ZnO magneto-optical glasses doped with Tb3+ and coded as GBPZT1-6 for Tb3+ doping concentrations ranging from 20 to 45 mol%, with a 5-mol% increment was investigated using theoretical and Monte Carlo simulation methods. The PHITS code and the Phy-X/PSD software was used to compute the mass attenuation coefficient (MAC) and other interaction quantities of the glasses for 0.015–15 MeV photons. Both methods' MAC data agree to within 2.90% of each other. At 0.015 MeV, the value of MAC is 59.9674 cm2/g, 64.1777 cm2/g, 67.6697 cm2/g, 70.6128 cm2/g, 73.1271 cm2/g and 75.2998 cm2/g for GBPZT1, GBPZT2, GBPZT3, GBPZT4, GBPZT5 and GBPZT6, respectively. The linear attenuation coefficients of the GBPZT glasses changed from 0.1340 to 247.5640 cm−1, 0.1490 to 286.8040 cm−1, 0.1650 to 326.6350 cm−1, 0.1790 to 365.7810 cm−1, 0.1990 to 413.9290 cm−1, and 0.2190 to 463.9450 cm−1 for GBPZT1, GBPZT2, GBPZT3, GBPZT4, GBPZT5, and GBPZT6. Comparatively, the photon attenuation abilities increase linearly as the density and Tb 2 O 3 content of the glass system increased. Hence, GBPZT6 has the highest mass and linear attenuation coefficients, while GBPZT1 has the least. The BPZT glasses have better photon absorbing capacities compared to ordinary concrete and some other conventional shielding materials, thus making them attractive choice in radiation protection functions. • Radiation shielding capacity of germinate glasses is estimated. • Monte Carlo simulations are carried out. • A good agreement between the theory and the simulation. • GBPZT6 glass system has a potential use in nuclear applications. [ABSTRACT FROM AUTHOR]

In this this paper, five transparent and non-toxic glasses with the chemical identity : 75TeO 10MoO 3 10BaO (5- x)Sm 2 O 3 x Bi 2 O 3 with x = 0 (TMBS-0Bi), 2 (TMBS-2Bi), 4 (TMBS-4Bi), 4.5 (TMBS-4.5Bi), and 5 (TMBS-5Bi) were synthesized using analytic grade chemicals following the melt and quench process. The glasses were characterized for their physical, optical, structural and gamma radiation attenuation attributes. The glasses appear transparent with colour gradient dictated by chemical content. XRD data and analysis confirm the glassy nature of the prepared glasses. As the Bi 2 O 3 content increased, the glass density increased from 5.46 to 5.64 g/cm3. The direct optical bandgap also showed variations with TMBS-5Bi having the highest value of 2.56 eV. The mass attenuation coefficient (µ / ρ) of the glasses was determined through FLUKA simulation and direct XCOM calculations. Results showed great agreement between µ / ρ obtained from both methods. The analysis of photon response parameters of the glasses indicated energy and chemical content variations for photon energies 15–15000 KeV. Generally, parameters relating to gamma ray absorption show improvement as Bi 2 O 3 was enhanced in the glasses. therefore, TMBS-5Bi and TMBS-0Bi is the best and weakest photon absorber among the prepared glasses. The TMBS-5Bi offer good alternative as a transparent and environmentally friendly glass for radiation control applications. The TMBS-XBi glasses are attractive optical materials on one hand, they are also considered candidates in radiation protection functions. [ABSTRACT FROM AUTHOR]

The variation in dosimetric parameters such as mass attenuation coefficient, half value layer factor, exposure buildup factor, and the photon mean free path for different oxide glasses for the incident gamma energy range 0.015–15 MeV has been studied using MicroShield code. It has been inferred that the addition of PbO and Bi 2 O 3 improves the gamma ray shielding properties. Thus, the effect of chemical composition on these parameters is investigated in the form of six different glass compositions, which are compared with specialty concrete for nuclear radiation shielding. The composition termed ‘Glass 6’ in this paper has the highest mass attenuation and the smallest half value layer and may have potential applications in radiation shielding. An example dry storage cask utilizing an additional layer of Glass 6 as an intermediate shielding layer, simulated in MicroShield, is capable of reducing the exposure rate at the cask surface by over 20 orders of magnitude compared to the case without a glass layer. Based on this study, Glass 6 shows promise as a gamma-ray shielding material, particularly for dry cask storage. [ABSTRACT FROM AUTHOR]

The high mass density that often characterize TeO 2 -based glasses makes them potentially useful in radiation shielding applications. In this paper, three ternary glass types defined by the chemical formula: (90 − x)TeO 2 - x ZnO-3La 2 O 3 for x = 35 (TZL-A1), 15 (TZL-A2), and 5 mol% (TZL-A3) were considered for optical and gamma radiation absorption study. The reflection loss (RLoss), metallization criterion (M), optical transmission (TOpt.), optical dielectric constant (εoptical), and static dielectric constant (εSta.) were the optical parameters estimated for the glasses. Also, gamma radiation shielding ability of the glasses were assessed through computation of mass attenuation coefficient μ m for energies 0.015 − 15 MeV using FLUKA simulations and XCOM computation. The RLoss is 0.105, 0.117 and 0.121 for TZL-A1 – TZL-A3, respectively while TOpt. is 0.809, 0.791 and 0.784 in the same order. The metallization criterion (M) is 0.513, 0.488 and 0.478 for TZL-A1, TZL-A2 and TZL-A3, respectively. The optical dielectric constant (εoptical) of TZL-A glasses is 2.849, 3.149 and 3.272 while the static dielectric constant (εSta.) is 3.849, 4.149 and 4.272 for TZL-A1, TZL-A2 and TZL-A3, respectively. Also, The value of μ m varies between 0.03309 and 47.90855 cm2/g, 0.03332 and 46.67536 cm2/g, and 0.0333 – 43.12055 cm2/g for decreasing ZnO content accordingly. Computed value of the Z eff falls between 22.74 and 49.74 for TZL-A1, 23.34–51.07 for TZL-A2 and 23.61–51.59 for TZL-A3. Other computed photon shielding quantities shows that higher TeO 2 content improves the shielding ability of the glasses. The present glasses showed superiority compared to some existing and popular shields such as ordinary concrete, commercial RS-253 and RS-360 glass shields. These glasses thus present better alternative materials which could be used in the implementation of an efficient photon collimator or biological shields in laboratories, industries, and medicine where gamma radiation are adopted for diverse applications. [ABSTRACT FROM AUTHOR]

This paper evaluates the γ-radiation shielding traits of some new types of borate glasses of composition (70–x)B 2 O 3 –10Bi 2 O 3 –10BaO–10CdO–xPbO (where 0 ≤ x ≤ 20 mol%) prepared using melt quenching method. As-quenched samples were characterized to determine the effects of various PbO contents on their γ-radiation shielding properties. XRD patterns of the samples verified their amorphous nature. The Phy-X and XCOM was used to compute the mass attenuation coefficients of the glasses and then compared with the experimental data. The γ-radiation shielding performance of the proposed glasses were evaluated in terms of diverse attenuation parameters like mean free path, half and tenth value layer, atomic cross-section, electronic cross-section, effective atomic number and effective electron density. The γ-radiation shielding performance of the glasses were significantly improved with the increase of PbO contents. This new borate glass system is established to be advantageous for the radiation shielding applications. • The borate glass samples with different PbO content were prepared by the standard melt-quenching method. • The μ/ρ values of the glasses were increased with the increase of the PbO content. • The relatively higher Zeff at lower energies due to the dominance of PE effect. • Promising HVT and TVL achieved with the new prepared glasses. • The proposed glass improves the efficiency of IR shielding material. [ABSTRACT FROM AUTHOR]

Abstract: The aim of this work was to develop a method to correct the absorbed radiation (the mass attenuation coefficient curve) in low energy (E <30keV) applied to a biological matrix based on the Rayleigh to Compton scattering ratio and the effective atomic number. For calibration, scattering measurements were performed on standard samples of radiation produced by a gamma-ray source of 241Am (59.54keV) also applied to certified biological samples of milk powder, hay powder and bovine liver (NIST 1557B). In addition, six methods of effective atomic number determination were used as described in literature to determinate the Rayleigh to Compton scattering ratio (R/C), in order to calculate the mass attenuation coefficient. The results obtained by the proposed method were compared with those obtained using the transmission method. The experimental results were in good agreement with transmission values suggesting that the method to correct radiation absorption presented in this paper is adequate for biological samples. [Copyright &y& Elsevier]

Abstract: In this paper bulk sample prompt gamma neutron activation analysis (BSPGNAA) was applied to aqueous sample analysis using a relative method. For elemental analysis of an unknown bulk sample, gamma self-shielding coefficient was required. Gamma self-shielding coefficient of unknown samples was estimated by an experimental method and also by MCNP code calculation. The proposed methodology can be used for the determination of the elemental concentration of unknown aqueous samples by BSPGNAA where knowledge of the gamma self-shielding within the sample volume is required. [Copyright &y& Elsevier]

Abstract: The mass energy absorption, the mass energy transfer and mass absorption coefficients have been widely used for problems and applications involving dose calculations. Direct measurements of the coefficients are difficult, and theoretical computations are usually employed. In this paper, analytical equations are presented for determining the mass energy transfer and mass absorption coefficients for gamma rays with an incident energy range between 0.4 and 10MeV in nitrogen, silicon, carbon, copper and sodium iodide. The mass absorption and mass energy transfer coefficients for gamma rays were calculated, and the results obtained were compared with the values reported in the literature. [Copyright &y& Elsevier]

This paper investigates the influence of lead monoxide (PbO) content on the gamma ray attenuation coefficients of boro-telluro-phosphate glasses. The MCNP5 simulation code has been applied to estimate the mass attenuation coefficients (μ/ρ) of Sm3+ doped (60-x)B 2 O 3 -xPbO-14TeO 2 -10P 2 O 5 -7.5BaO-7.5CdO-1Sm 2 O 3 (x = 0, 10, 20, 30 and 40 wt%) glass system within 0.02–10 MeV photon energy range. The MCNP5 simulated results are accord with the theoretical XCOM results perfectly. The results show that the increasing content of PbO in the glass compositions can improve the gamma ray shielding capability of the studied glasses. With the biggest content of PbO in Pb40B20 glass, superior HVL and Z eff values are observed. The values of HVL for Pb40B20 glass vary from 0.0035 to 3.6824 cm, and the values of Z eff vary from 25.94 to 70.05 depending on the photon energy 0.02–10 MeV. In addition, the boro-telluro-phosphate glasses have been compared with types of commercial concretes and glasses in terms of HVL. • μ/ρ, Z eff , N eff, EBF, HVL and MFP for Sm3+ doped lead boro-telluro-phosphate glasses have been calculated. • The maximum value for μ/ρ and Z eff was found for the glasses with the highest PbO oxide. • MCNP code and XCOM software were used to calculate (μ/ρ) at different energies. • With the addition of PbO, the shielding properties of the prepared glasses were improved. [ABSTRACT FROM AUTHOR]

This paper presents the results of a study of the properties of a series of 0.5Bi 2 O 3 -(0.5-x)WO 3 -xPbO glasses obtained by sintering. Using the X-ray diffraction method, an amorphous glass structure is installed. Analysis of structural and optical characteristics showed that an increase in PbO concentration leads to an increase in density, as well as a decrease in the metallization criterion. It was found that an increase in PbO leads to a decrease in the band gap and an increase in the linear refractive index, a change in which indicates a change in the degree of structural disorder caused by impurities or electron traps. During experiments to determine the gamma-ray shielding efficiency, it was found that the best shielding efficiency is possessed by 0.5Bi 2 O 3 -0.125WO 3 -0.375PbO glasses, for which the mass attenuation coefficient is 3.6 times higher than that for 0.5Bi 2 O 3 -0.5WO 3 glasses. The results obtained are in good agreement with the literature data for similar structures, and the proposed method of obtaining can be used in the future for the technological process of industrial production of radiation-protective materials. • The results of a study of the properties of a series of 0.5Bi 2 O 3 -(0.5-x)WO 3 -xPbO glasses. • The change in the value of the band gap and linear refractive index. • The radiation protection efficiency versus PbO concentration. • The dependence of changes in linear and mass attenuation coefficient of gamma radiation. [ABSTRACT FROM AUTHOR]

Polylactic acid (PLA) is a biodegradable organic acid of polymeric chain that has as chemical structure the monomer C 3 H 4 O 2 and it is one of the most used materials in rapid prototyping among 3D printers. Due to the ease of manufacturing PLA parts and because of its low atomic number, PLA can be used as holder to radiation source and detectors to establish fixed geometries in experiments using gamma radiation, hence the importance in knowing more about PLA characteristics. In this way, the novelty of this paper is to determine the mass attenuation coefficient of 3D printed PLA samples using gamma densitometry. A mathematical model was developed using MCNPX code and consisted of a PLA sample, a NaI(Tl) detector and gamma rays of 661.6 keV as radiation source (narrow beam). The mathematical model was experimentally validated using the same geometry and a lead collimator. Besides that, PLA weight fractions and density were also determined in order to use this information as input data in the MCNPX code. The obtained mass attenuation coefficients were in good agreement with the NIST theoretical reference value, presenting relative errors of 0.99% (MCNPX) and 2.00% (experimental). The proposed methodology was repeated replacing PLA for aluminum samples and comparing its results with NIST. In addition, the mass attenuation coefficient for some polymers was calculated using this model aiming to validate the geometry developed with MCNPX code. • Simulation of mass attenuation coefficients using MCNPX code. • Absorber material are 3D printed polylactic acid samples. • Experimental validation of the methodology using gamma densitometry. • Simulation of others absorber materials. [ABSTRACT FROM AUTHOR]

This paper focuses on the role of antimony oxide (up to 15 wt%) in the physical, structural, optical, and radiation attenuating characteristics of boro-bismuth glasses within B 2 O 3 -20Bi 2 O 3 - 20Na 2 O 2 - Sb 2 O 3 system. This glass system was prepared by melting at 1250°C and quenching into water. The physical properties were studied by measuring the density, molar volume, and x-ray diffraction for the prepared glass system. The structural features were investigated by determining packing density, passion ratio, oxygen packing density, and oxygen molar volume. The optical attributes were explored by evaluating bandgap, Urbach energy, refractive index, and other related parameters such as dielectric constant, reflection loss, molar polarizability, molar refractivity, optical dielectric constant, optical electronegativity, electron polarizability, optical basicity, metallization, and cut-off wavelength. On the other hand, the shielding properties of the prepared glasses were studied against different types of radiation such as gamma, electron, proton, and neutron beams. The radiation studies were carried out by utilizing Geant4 simulations and the newly developed Phy-X/PSD program. The radiation-shielding characteristics of the present samples were examined in terms of mass attenuation coefficient, stopping power, half value layer, removal cross section, mean free path, and effective atomic number of gamma, electron, and proton beams. The results showed that antimony oxide content had an important influence on the shielding ability against all of the types of radiations. Additionally, the obtained results were compared with those of standard radiation shields. It can be concluded that the present glasses have a promising future to be used as radiation shielding material, wherein the antimony oxide concentration can be balanced according to the desired application. [ABSTRACT FROM AUTHOR]