Mass Attenuation Coefficients Research Articles

Structural, thermal, and radiation shielding properties of B2O3-TeO2-Bi2O3-CdO-Tm2O3 glasses: The role of Tm2O3

This study presents a detailed investigation into the structural, thermal, and radiation shielding properties of a new glass composition, labeled as (50-x)B2O3 + 30TeO2 + 10Bi2O3 + 10CdO + x Tm2O3 (where x = 0, 1, 2, 3, 4, 5 mol %). Various radiation shielding parameters such as mass attenuation coefficient, linear attenuation coefficient, half-value layer, mean free path, effective atomic number, and absorbed equivalent dose rates for neutrons were determined through experimental measurements. The study also employed theoretical calculations to assess the exposure buildup factor and effective removal cross-section for neutrons. Additionally, the SRIM program was utilized to investigate mass stopping power and projected range for proton and alpha particles. The structural characteristics of the glasses were analyzed using XRD and FT-IR, while thermal properties were examined through Differential Thermal Analysis (DTA). FTIR analysis revealed distinctive bands corresponding to Bi—O, B—O—B, and Te—O bonds. Glass transition temperatures (Tg) increased with Tm2O3 content, ranging from 422 °C to 444 °C. The radiation shielding properties of bismuth boro-tellurite glasses showed that a dose of 1.2025 μSv/h emitted from a fast neutron source was absorbed by 35.1574 % in pure glass and 40.0391 % in glass doped with 5 mol% Tm2O3. Incorporating Tm2O3 into the glass matrix significantly improved the shielding and thermal properties, thus enhancing their potential for advanced high-energy radiation absorption. This investigation contributes to a deeper understanding of how Tm2O3 enhances the structural and thermal attributes of these glasses, positioning them as promising materials for radiation shielding applications.

Composite cellulose/bismuth/PVA nanocrystal for high-performance X-ray radiation shielding

The strong penetrating power of X-rays causes serious health problems. Longer exposure to radiation that penetrates normal cells can result in gene mutations, cancer, and even death. Protection against radiation exposure is necessary to prevent negative impacts from occurring. This research aims to make apron samples using a simple method based on cellulose as a matrix, bismuth as a filler with concentrations of 1 g, 0.75 g, 0.25 g and PVA acts as a binder that helps bind cellulose and bismuth particles into an effective X-ray radiation shield. The characterization carried out includes Fourier transform infrared (FTIR) to determine the functional groups and chemical composition of the sample, x-ray diffraction (XRD) to analyze the crystal size of the sample, and mobile x-ray with energies of 60, 70, and 80 keV to determine the radiation shielding performance. The findings of this study highlight that the optimal shielding properties were attained by employing a sample with the highest concentration of bismuth filler, specifically at 1 g. This material exhibits outstanding characteristics, including a high linear attenuation coefficient and mass attenuation coefficient of 0.68 cm−1 and 2.24 cm2/g respectively for an energy of 60 keV and especially low HVL (1.01 cm) and TVL (3.36 cm) values. These findings have significant implications for developing high-performance X-ray radiation shielding materials, particularly in industries where radiation exposure is a concern, such as the medical industry, research, and laboratories. The high tensile strength (2.83 N/mm2) and elongation (12.09 %) values as well as the low Young's modulus (0.108 N/mm2) values also indicate the flexibility of the resulting material, which could be beneficial for applications that require flexible shielding materials. The practicality of this research makes the audience feel that the findings are applicable and useful in real-world scenarios.

Investigation on luminescent characteristics of Tb3+/Dy3+co-doped boro-phosphate glass for cool white LED and radiation shielding applications

The Tb3+/Dy3+ co-doped Boro-Phosphate Glass (BPANZDyTb) was produced (40 B2O3 + 39P2O5 + 5 Al2O3 + 5 NaF + 10 ZnO + 0.5 Tb2O3 + 0.5 Dy2O3) using melt-quenching technique. X-ray diffraction measurements, Raman, and Fourier Transform Infrared were used to evaluate the structural behavior of the prepared glass. Powder-XRD spectra, in the 10–90° range showed that the prepared glass was amorphous. FTIR analysis reveals that the network contains a variety of structural groups, including B-O-B, BO4, BO, P-O, PO2, P-O-B, and PO4 units. The UV–visible diffuse reflectance spectroscopy was used to record and study the optical linear properties of Tb3+/Dy3+ co-doped Boro-Phosphate Glass (BPANZDyTb). The photoluminescence excitation peak was obtained at 348 nm. The emission peaks were located at 484 nm (4F9/2 → 6H15/2 → blue), 576 nm (4F9/2 → 6H13/2 → yellow), and 662 nm (4F9/2 → 6H11/2 → red). Tb3+ ions are located at 412 nm (5D3 → 7F5), 441 nm (5D3 → 7F4), 546 nm (5D4 → 7F5), and 625 nm (5D4 → 7F3). The result of CIE 1931 chromaticity coordinates indicate that the prepared glass is suitable material for cold white light emitting diode applications due to its color coordinates x = 0.3106 and y = 0.3240 and correlated color temperature (CCT) values about 6768 K. The gamma-ray parameters such as half-value layer (HVL), mass attenuation coefficient (μ/ρ), mean free path (MFP), and effective atomic number (Zeff) of the BPANZDyTb glass were studied using Phy-X software. The results of the gamma-ray parameter show that the Dy3+ ions and Tb3+ ions co-doped BoroPhosphate glass is an appropriate material for radiation shielding applications.

Structural, optical and attenuation properties analysis of iron-doped zirconium oxide nanoparticles for photocatalytic and radiation shielding applications

This manuscript explores the effects of iron doping on the structural, optical, and photocatalytic properties of ZrO2 nanoparticles (NPs) for photocatalytic applications. Techniques such as X-ray diffraction (XRD), Fourier transform infrared spectroscopy (FTIR), and UV–visible spectroscopy were used to investigate the characteristics of synthesized materials. The XRD pattern of ZrO2 indicates a pure monoclinic phase structure and strong diffraction orientation along the (1¯11) direction; with adding Fe with different concentrations, a new phase appeared, indicating ZrO2 NPs with tetragonal phase structure with strong diffraction orientation along the (101) direction as well as Fe concentrations increase, new phases appeared, namely α-Fe2O3, Zr3Fe, and Zr4Fe2O0.6. The observed trend in the crystallite size decreases from 25 nm to 13 nm with increasing Fe concentrations. The NPs’ optical bandgap was found to be 4.28 eV, reducing to 2.93 eV as the concentration of Fe increased. This value is in good agreement with those previously published for photocatalytic applications. The photocatalytic performance was determined and found to obey a first-order rate constant where the best-performing sample was FZO-10 with methylene blue degradation (94 %) and k values (36.2 × 10 −3 min −1), respectively. Additionally, the mass attenuation coefficient and half-value layer analysis revealed significant attenuation properties, showing a consistent decrease in GMAC with increasing gamma energy and highlighting the impact of ZrO2 concentration on gamma-ray shielding effectiveness. The outcomes demonstrate that Fe doping has a significant effect and has the potential to improve ZrO2-based photocatalytic applications’ performance.

Experimental and theoretical results of gamma shielding features for copper based shape memory alloys

In this study, the gamma ray attenuation characteristics for CuAlNi shape memory alloys with different proportions of Sn doping was investigated. We determined the mass attenuation coefficient (μ/ρ) of CuAlNiSn alloys both experimentally and theoretically within an energy range of 59.5–1332.5 keV. The experimental measurements were made using a high purity Germanium detector (HPGe) and theoretical calculations were made using WinXCOM program. To evaluate the gamma radiation shielding abilities of the alloy samples, the obtained (μ/ρ) values were used to determine the gamma protection parameters μ, HVL, TVL, MFP, and Zeff. In addition, the radiation protection efficiency (RPE) parameter was determined using gamma ray intensities in the absence and presence of the attenuator. Further analysis of the samples was conducted using a Rigaku Miniflex 600 model computer-controlled X-ray diffractometer (CuKα & λ = 1.5405 A0). The crystallographic structure of the alloys before and after irradiation was investigated. Other analysis which include EDX analysis (to investigate the chemical content) and SEM analysis (to investigate the microstructure) were conducted. According to result outcomes, gamma ray radiation did not affect the shape memory properties of structure. Another interesting observation is that, the radiation attenuation properties increase with increasing Sn concentration. Finally, we discovered that the CuAlNiSn4 alloy (which has the highest doping rate) provides good protection especially at low energy levels.

Investigation of the radiosensitive properties of curcumin and temozolomide

Radiotherapy, one of the cancer treatment strategies, uses ionizing radiation to destroy cancer cells. It is very important to know the photon interaction parameters of curcumin, which has both anti-cancer and cancer-protective properties, to determine the penetration and energy accumulation in the interaction of radiation with tissue. In this work, the linear attenuation coefficient (LAC, μ), mass attenuation coefficient (MAC, μ/ρ), mean free path (MFP), half value layer (HVL), effective atomic number (Zeff), and electron density (Nel) of curcumin and temozolomide have been determined experimentally at 53.16 keV, 80.99 keV, 276.39 keV, 302.85 keV, 356.61 keV and 383.84 keV photon energies emitted from Ba133 point source by using the ULEGe detector. Besides, the radiation interaction parameters were calculated theoretically using the EpiXS software program. Also, the exposure buildup factors (EBF and EABF) of these compounds were determined up to 40 mfp in the energy range 0.015–15 MeV. The experimental and theoretical mass attenuation coefficients have been found to agree. The gamma-ray absorption efficiency of curcumin is approximately 3.89% higher than that of temozolomide. Temozolomide has approximately 25.6% higher fast neutron removal cross-section than curcumin.

Investigation of structural, optical characteristics of Gd3+ doped phosphate glass for radiation shielding applications

Gadolinium doped phosphate glass was created with a composition of 70 P2O5 + 5Al2O3 + 5 Ba2CO3 + 9 KF2 + 5 MnO2 + 5 SnO+1 Gd2O3 by using the melt-quenching process. The prepared glass sample’s amorphous nature was confirmed by the X-ray diffraction analysis. FT-IR examination confirms the presence of phosphate functional groups. Glass’s optical band gap was found to be 3.5 eV using Tauc’s plot method. The photoluminescence analysis indicates that the emission band at around 311 nm. The Commission International de I’Eclairage (CIE) was employed. It was identified that the computed chromaticity coordinate values (x = 0.3164 and y = 0.3371) were situated in the summer sunlight zone, close to the white light region. The attenuation capabilities of the gadolinium-doped phosphate glass sample were validated by the gamma ray shielding parameters. The mass attenuation coefficient and Mean free path of the prepared glass were fund to be 4.41 × 105 cm2/g at 0.015 MeV and 12.4 cm at 15 MeV respectively. In terms of infiltration deepness up to 40 MFP, the energy-related energy buildup factor (EBF) and energy absorption buildup factor (EABF) of glasses were calculated using the five (a, b, c, d, and Xk) parameters of the G-P fitting scheme. All of the results show that the synthetic glass can be used as shielding materials against gamma radiation.

Investigation of the gamma ray shielding properties of Epoxy based on Bi2O3/GO nanocomposite

Abstract One of the important carbon materials, graphene oxide (GO), has several oxygen-containing functional groups. Due to its unique structure, it has attracted increasing interest in multidisciplinary studies of physical and chemical attributes. In this work, Bismuth Oxide nanoparticles (Bi2O3) is prepared and functionalized with graphene oxide nanosheets (Bi2O3-GO). The Bi2O3 and Bi2O3-GO nanocomposite were mixed with epoxy by changing the percentages to 1%, 2.5%, 5%, and 10%. The study used a hyper-pure germanium detector to investigate the attenuation characteristics of the prepared samples. Ba133, Cs137, and Co60 point sources were used at photon energies of 81, 276, 302, 356, and 383 keV for Ba133, 661 keV for Cs137, and 1173 and 1332 keV for Co60. The linear attenuation coefficient, mass attenuation coefficient, half-value layer, and tenth-value layer were estimated to investigate the radiation shielding characteristics of the prepared samples. The linear attenuation coefficient (μ) values varied from 0.45 to 0.88, 0.23 to 0.89, and 0.31 to 0.77 for Ba133, Cs137, and Co60, respectively. The mass attenuation coefficient (μm) values varied from 0.18 to 0.50, 0.19 to 0.50, and 0.15 to 0.50 for Ba133, Cs137, and Co60, respectively. Half-value layer (HVL) values varied from 0.79 to 1.55, 0.78 to 3.07, and 0.9 to 2.26 for Ba133, Cs137, and Co60, respectively. Tenth-value layer (TVL) values varied from 2.61 to 5.16, 2.58 to 10.19, and 2.98 to 7.51 for Ba133, Cs137, and Co60, respectively.

Yttria-doped geopolymers: Environmentally friendly and effective materials for shielding concrete in gamma radiation facilities

The use of geopolymer in place of ordinary Portland cement for concrete design and constructure is gaining attraction due to environmental and health considerations. Geopolymers must have high gamma radiation shielding competence in order for them to be useful for radiation shielding concrete. In an attempt to improve the gamma absorption capacity of a metakaolin-based geopolymer matrix, 10 % (GEO-10Y), and 20 % (G-20Y) yttria (Y2O3) was mixed with GEO through a solid-state reaction process. In this study, the influence of adding yttria on the physical and gamma shielding parameters of GEO was investigated. The densities of GEO, GEO-10Y and GEO-20Y were obtained as 2.28, 2.52 and 2.37 g/cm3, respectively. Through simulation using FLUKA code, the mass attenuation coefficients (MAC) and other relevant shielding quantities were estimated. The MACs of GEO, GEO-10Y, and GEO-20Y were within the range of 0.0213–6.6429 cm2/g, 0.0282–13.3923 cm2/g, and 0.0291–14.5136 cm2/g, respectively. The addition of yttria improved the gamma photon shielding competence of the metakaolin-based geopolymer by increasing the MAC and reducing photon buildup factors within 15 keV–15 MeV photon energy range. The shielding effectiveness of the yttria-doped GEO compares well with conventional shielding materials. Yttria-doped geopolymer can be used to produce effective and environmentally-friendly gamma shielding concrete.

A closer look at the fabrication of some doped metal ions in borophosphate glass system and their structural, elastic, optical, and gamma-ray shielding characteristics

Borophosphate host glasses doped with zinc oxide (ZnO), titanium dioxide (TiO2), tellurium dioxide (TeO2), or cerium oxide (CeO2) were synthesized using rapid quenching techniques. Fourier transform infrared (FTIR) spectra, along with deconvoluted FTIR spectra, were recorded in the 400–4000 cm−1 range. Using the models of Tauc and Urbach, the optical energy band gaps of these glasses were found to be 3.212, 3.289, 3.262, 3.087, and 2.475 eV respectively. Due to the incorporation of different metal ions into the prepared glasses, the density increased and the molar volume decreased, making the glass structure highly compact. Since the elastic moduli are directly related to the average cross-link density, the shear and longitudinal moduli show a forward proportionality with the average cross-link density. Detailed reporting focused on the mass attenuation coefficients (μm) and exposure build-up factors (EBF), crucial for evaluating the shielding properties of the material within the energy range of 0.015–15 MeV and penetration depth up to 40 mean free paths (mfp). Glass samples doped with tellurium dioxide exhibited the highest gamma attenuation due to their higher effective atomic number compared to the other samples. Compared to Portland concrete, the prepared glass composites showed higher mass attenuation coefficients across the entire investigated energy range. These results suggest that although Borophosphate glasses doped with cerium oxide have preferred mechanical properties compared with the other prepared glasses, Borophosphate glasses doped with tellurium dioxide could serve as transparent shielding material for medical applications due to their higher attenuation coefficient.

Gamma ray shielding ability of Y3+ doped borophosphate glasses

Abstract Four selected Y2O3 doped borophosphate glass samples are prepared using melt quench technique. The structural properties such as density and molar volume are measured. The density (ρ) increases from 3.1384 to 3.4613 g/cm3 whereas molar volume (Vm) decreases from 60.84 to 55.00 cm3 mol−1 with addition of Y2O3 cm3 mol−1 content. The lattice of the glasses has been tested via X-ray diffraction which is a good technique for confirming the structural properties of these glasses and FTIR spectra. In addition, radiation shielding parameters for glasses were performed theoretically utilizing XCOM program for various gamma ray energy and experimentally using NaI(Ti) scintillation detector, The glasses were irradiated using energies 0.664, 1.174 and 1.334 MeV emitted by Cs-137 and Co-60 radioactive point sources respectively. Shielding parameters as leaner (μ), mass attenuation coefficients (μ/ρ) and half value layer (HVL), tenth value layer (TVL) and mean free path (MFP). The concentration of Y2O3 increases the (μ/ρ) increases, the HVL, TVL, and MFP values have inverse way. Superior radiation shielding is confirmed by the glass sample containing (3%, mole) of yttrium oxide. The results show that the borophosphate glasses doped with Y2O3 can be used to shield gamma rays.

γ-radiation-induced centers in irradiated perovskite SrCeO3 and their role in thermally stimulated reactions: Fluorescence, thermally stimulated luminescence, electron paramagnetic resonance and shielding studies

One promising host for actinide radioactive wastes is orthorhombic perovskite-type oxide. Perovskite SrCeO3 ceramic was synthesized by nitrate-fuel combustion, which includes the organic fuel glycine. Powder X-ray diffraction was utilized to determine the structural features, and γ-radiation-induced changes and shielding properties were investigated in perovskite SrCeO3. In a mixed-phase sample, a bright sky-blue luminescence was observed, and two thermoluminescence (TL) peaks were seen in irradiated SrCeO3 ceramic. Electron paramagnetic resonance (EPR) spectrum in γ-irradiated SrCeO3 ceramic had contributions from five defect centers. Center I having an isotropic g-value equal to 2.0283, is ascribed to an O− ion, while center II with an axial g-tensor with principal values g|| = 2.0224 and g⊥ = 2.0068 is determined as an O2− ion. O− ion relates to the TL peak at 215 °C. Center III with a g-value equal to 2.0009 is identified as an F+ center and is related to the 185 °C TL peak. The defect center associated with center IV is also identified as an F+ center. An additional defect center in the higher field region of the spectrum is assigned to an F+ center, and the center results from an F-center (oxygen vacancy with two electrons). The mass attenuation coefficients, effective atomic numbers, and half-value layer thicknesses concerning shielding property effectiveness were computed and it was found that the perovskite SrCeO3 ceramic provided superior γ-shielding properties.

Advanced polymeric matrix utilizing nanostructured bismuth and tungsten oxides for gamma rays shielding

In this study, the shielding properties of novel polymer composites, developed by integrating glycidyl methacrylate with nanoparticles of bismuth oxide (Bi2O3) and tungsten oxide (WO3), were explored. The ability of the composites to attenuate gamma radiation was evaluated by measuring the emissions from Ba-133, Co-60, Cs-137, and Na-22. X-ray diffraction (XRD) spectra were obtained for both the pure polymer glycidyl methacrylate and the samples containing nanostructures of Bi2O3, Bi2O3/WO3, and WO3, and scanning electron microscopy (SEM) was used to analyze the samples. The incorporation of Bi2O3 and WO3 nanoparticles into the polymer glycidyl methacrylate matrix significantly enhanced the composites' ability to attenuate gamma radiation, as demonstrated by the increased linear and mass attenuation coefficients. The results showed good agreement between the experiment and the XCOM database. The composites exhibited significant efficiency in attenuating lower-energy gamma rays, which is particularly advantageous in the medical and nuclear industries.

Effect Gamma-ray on structure and mass attenuation coefficient of Hydroxyapatite Ca10(PO4)6(OH)2, in Bovine Bone

Hydrothermal treatment procedures were employed, to generate hydroxyapatite (Ca₁₀(PO₄)₆(OH)₂ ,(HAP) powder, from the femur and ribs of bovine bone samples. This investigation delves into the effect of gamma rays, from a Cs-137 activity equal to 220 µCi at integral doses of 20 kGy, on the surface structures, vibration properties, and attenuation coefficient of HAP, in the bovine femur bone and ribs. The mass attenuation coefficients for HAP powder were registered as E= 511 keV, with 1276 keV gamma energy released from the 22Na radioisotope, and 662 keV gamma energy released from the 137Cs radioactive isotope. We used the Nist XCom program to calculate the mass attenuation coefficient of HAP before and after radiation for photon energies ranging from 0 keV to 100 keV.

Investigation on radiation shielding potentials of barium calcium aluminosilicate glass material using silicon carbide nanotubes reinforcement

This work investigated the gamma ray attenuation power of barium calcium aluminosilicate glass by using silicon carbide nanotube modifiers. Shielding efficiency of BaO–15CaO–5Al2O3–10B2O3–35SiO2 was investigated by adding different concentrations of silicon carbide nanotubes (10, 15, 20, 25 mol %). Amorphous and fine characteristics of the prepared glass materials were analyzed using XRD and FTIR techniques. In the results obtained, absence of sharp peaks in the XRD pattern revealed that the prepared glass was amorphous. Analysis of the radiation shielding properties was tested against gamma radiation by using PHY-X/PSD software. Various shielding parameters such as linear attenuation coefficient, mass attenuation coefficient, half value layer, tenth value layer, mean free path, and effective atomic number were determined to access the radiation shielding strength of the prepared samples. From the obtained results, composites of barium calcium aluminosilicate and silicon carbide nanotubes (sample 1) with higher values of mass attenuation coefficient (32.92 cm2/g) and effective atomic number (52.02) provided superior gamma ray attenuation. Results also revealed that the density and chemical composition of the prepared glass samples strongly influence photon interactions and weakly influence electronic interactions during the photon attenuation process. The results demonstrated that increasing the weight fractions of silicon carbide nanotubes in the glass samples increases the shielding properties.

Simulation and calculation of the radiation attenuation parameters of newly developed bismuth boro-tellurite glass system

This paper presents a comprehensive simulation and calculation study of the radiation attenuation parameters for a newly developed bismuth boro tellurite glass system. Through advanced computational modeling and theoretical analysis, linear and mass attenuation coefficients (μ and μ/ρ), and other key radiation attenuation parameters of the studied glass system are thoroughly investigated across a range of photon energies. Utilizing state-of-the-art simulation techniques and theoretical models, the radiation shielding effectiveness of the glass system is evaluated, offering insights into its potential applications in radiation protection and shielding. We found that the ΣR values for fast neutrons are 0.10013, 0.10221, 0.10953, 0.11347 and 0.11383 cm−1 for BTBiBV-1, BTBiBV-2, BTBiBV-3, BTBiBV-4, and BTBiBV-5, respectively. The results of this study contribute to the understanding of the radiation attenuation properties of bismuth boro tellurite glasses and provide valuable information for their utilization in various fields, including medical imaging, nuclear power, and industrial radiography. Additionally, accurate modeling and characterization of attenuation parameters across different photon energies are crucial for designing effective radiation protection strategies and ensuring the safety of personnel and equipment in radiation environments.

Effects of MoO3 on the structural, physical, mechanical, optical, and ionizing shielding of borate-germanate-telluride glass system

In this investigation, a group of different concentrations of molybdenum trioxide-doped borate-germanate-telluride glasses have been synthesized. Four glasses with a composition formula of (35-x) B2O3-20TeO2-10GeO2-35MgO-xMoO3 where x values vary between 5 and 20 mol % have been achieved using the melt-annealing process. X-ray diffraction for the current M1 sample was utilized to prove the glassy nature. FTIR has been measured to understand the glass structure. Many functional group and vibrational bonds were observed. The optical parameters for B2O3-TeO2-GeO2-MgO-MoO3 glass samples were calculated based on absorption spectra recorded in the 200–1100 nm wavelength range. The optical electronegativity (χ) and optical basicity (Λ) were calculated as critical parameters that can be used to evaluate the glass structure. Physical parameters like density, molar volume (Vm), packing density (Vt), oxygen packing density (OPD), and oxygen molar volume (OMV) were measured and calculated. Hardness (H), Poisson ratio (σ), Fractal bond conductivity (d), and elastic moduli of M1, M2, M3, and M4 glass samples were calculated. Mass attenuation coefficients (MAC) for four synthesized glass samples were reported along with linear attenuation coefficient (LAC) as a function of photon energy. Based on the transmission factor TF %, it shows extremely low percentages at the lowest energy region, dropping to less than 1 % at 0.015 MeV up to 0.08 MeV in all samples. The radiation protection efficiency (RPE) was examined to measure the samples' capacity to attenuate ionizing radiation.

Design and characterization of borosilicate glass modified with TiO2 for enhanced optical and radiation shielding applications

This work investigates the potential of borosilicate glass doped with titanium dioxide (TiO2) for radiation shielding applications. The study explored the impact of varying TiO2 concentrations on the glass structure, optical properties, and radiation shielding effectiveness. X-ray diffraction (XRD) and Raman spectroscopy confirmed the amorphous nature of the glasses. The addition of TiO2 affected the glass network structure, as evidenced by changes in the Raman spectra and density measurements. UV–Vis spectroscopy revealed a red shift in the absorption edge (416–481 nm) and a decrease in the indirect optical band gap (2.91–2.70 eV) with increasing TiO2 content. The refractive index also increased from 2.54 to 3.54 with TiO2 concentration. The mass attenuation coefficient (MAC) and linear attenuation coefficient (LAC) increased significantly with TiO2 addition, indicating enhanced radiation attenuation capability. The inclusion of TiO2 reduced the half-value layer (HVL), tenth-value layer (TVL), and mean free path (MFP), while increasing the effective atomic number (Zeff). The effective electron density (Neff) and effective conductivity (Ceff) showed a slight increase with TiO2 content. Energy build-up factors (EBF and EABF) indicated a higher rate of radiation intensity increase and energy absorption within the glass due to the presence of TiO2. Finally, the incorporation of TiO2 into borosilicate glass offered a promising approach to developing improved optical and radiation shielding glasses.

An in-depth analysis of the optical and radiation shielding characteristics of PbF2-MoO3-Bi2O3-B2O3 glasses

This study investigates the optical and radiation shielding characteristics of different glass systems, such as PbF2, MoO3, Bi2O3, and B2O3, with varied concentrations of PbF2. The glass samples were manufactured by a melt quenching technique, with a composition of 20 Bi2O3—10 MoO3 - (70-x) B2O3-x PbF2, where x is a value between 0 and 20 mol%. The optical properties were evaluated using UV–vis spectrophotometry, while the radiation shielding parameters were calculated using Phy-X/PSD software. The mass attenuation coefficient (MAC) at 0.015 MeV exhibited an increase from 34.101 to 54.190 cm2 g−1 as the quantity of PbF2 rose. At an energy of 15.0 keV, the effective atomic number (Zeff) increased from 74.11 to 76.63, while the half-value layer (HVL) decreased from 0.00263 cm to 0.00188 cm. The values of the optical band gap (Eg) ranged from 2.577 to 2.105 eV, showing a decrease as the PbF2 content rose. The study shows that these glass structures can be utilized in advanced technological applications that demand higher optical and radiation shielding properties, thanks to their improved characteristics with increasing PbF2 content.

Enhanced gamma-ray shielding capabilities of Bi-Se-Ge chalcogenide glasses: analytical and simulation insights

This study investigates the gamma-ray shielding properties of Bi-Se-Ge chalcogenide glasses using advanced computational tools. The Phy-X/PSD and FLUKA programs were utilized to determine critical shielding parameters such as linear attenuation coefficient ( GLAC ), mass attenuation coefficient ( GMAC ), half-value layer ( GHVL ), mean free path ( GMFP ), and effective atomic number ( Zeff ). Our findings reveal that these glasses exhibit superior shielding capabilities compared to traditional materials. For instance, the GMAC values for the glasses ranged from 101.472 cm2/g to 177.475 cm2/g at a photon energy of 0.015 MeV. Additionally, the GHVL values decreased significantly with increasing Bi content, from 4.082 cm to 3.104 cm at an energy level of 15 MeV. The effective atomic number ( Zeff ) also increased from 36.12 to 53.23 with higher Bi concentrations. These insights, derived from precise computational analysis, highlight the potential of Bi-Se-Ge glasses for applications in radiation protection. The discussion also examines the impact of substituting Bi atoms with Se on the shielding capabilities of the original Bi-Se-Ge glass.Future work will focus on experimental validation of these results to further substantiate our findings.