Radiation Shielding Characteristics Research Articles

Influence of Engineering Properties on Radiation Shielding Characteristics of Some Egyptian Granitic Rocks as Potential Materials

Influence of Engineering Properties on Radiation Shielding Characteristics of Some Egyptian Granitic Rocks as Potential Materials

Effect of bismuth oxide on radiation shielding and interaction characteristics of polyvinyl alcohol-based polymer: Potential use in medical apron design

This study evaluated radiation shielding and interaction characteristics of polyvinyl alcohol (PVA) polymer separately doped with 10% and 20% Bi2O3 respectively for medical apron design and shielding special electronic installations. Prepared samples were characterized by scanning electron microscopy (SEM) and energy dispersive spectrometry (EDS). The EDS results showed that Carbon (C), Oxygen (O), and bismuth (Bi) elements were the predominant elements present in the prepared samples. The SEM result displaced surface irregularities due to a special bonding matrix between PVA and Bi2O3. Mass attenuation coefficient (MAC), effective atomic number (Zeff), Half value layer (HVL), Mean free path (MFP), Fast neutron removal cross-section (R), Total Mass Stopping Power (TSP), and photon Range (R) of the prepared polymer composites (PV-1Bi and PV-2Bi) were evaluated with XCOM and PHITS computer programs. Results showed that the MAC of the prepared polymer samples was significantly higher than some recently developed composites at 0.662 MeV and 1.25 MeV gamma energy. Therefore, polyvinyl alcohol (PVA) polymer doped with Bi2O3 should be deployed in medical apron design and shielding special electronic installations where flexibility and high adhesion abilities are crucial.

A closer look to dose assessment and radiation shielding characteristics of concrete doped magnetite irradiated with 252Cf mixed radiation radionuclide: A Watt Fission approach and Doppler effect

Nuclear radiation emitted by fusion reactors, nuclear power plants, and medical establishments presents potential risks to living organisms personnel, necessitating the implementation of protective measures. To enhance radiation protection for patients workers, various materials can be utilized. Concrete, augmented with various additives, has historically acted as a shielding material. Hence, recent research has predominantly focused on enhancing concrete's ability to attenuate the harmful energy emitted by nuclear sources through modifications to its composition. Accordingly, in the present work, the dose evaluation and radiation shielding characteristics of a range of concrete magnetite (CM) formulations designated as CM-0 (control sample), CM-25, CM-50, CM-75, and CM-100 have been analyzed using MCNPX Monte Carlo (MC) approach and theoretical computations concerning 252Cf mixed radiation radionuclide. In this work, the Watt Fission distribution was employed to derive the neutron spectrum of CM samples, and findings have been thoroughly elucidated in the presence and absence of the specified samples. Then, utilizing the Doppler Effect, the gamma photon spectrum within shielding materials exposed to a spontaneous fission 252Cf source is extracted and characterized. Estimation of Half Value Thickness (HVT) and Mean Free Path (MFP) are provided across a broad spectrum of energy levels. The analysis confirms the successful development of a new type of concrete magnetite (CM) sample that exhibits lower radiation exposure compared to the control sample. This study offers valuable insights into the use of concrete in shielding against mixed radiation radionuclides and opens the door for future research involving similar materials. Specifically, the CM-100 sample demonstrated the lowest half-value thickness (HVT) and provided the most effective reduction of both neutron and gamma radiation. The findings suggest that increasing the concentration of magnetite in concrete greatly enhances its ability to shield against mixed neutron-gamma radiation. This innovation has promising potential for applications in radiation protection, particularly within nuclear reactors and medical facilities. The CM-100 sample showed a notable improvement, achieving an HVT of 0.012 cm and a dose rate reduction of 2.95 × 10−9 Sv.h−1, in contrast to the control sample (CM-0), which had an HVT of 10.358 cm and an equivalent dose rate of 2.84 × 10−9 Sv.h−1. These results underscore the superior shielding properties of the magnetite-doped concrete formulations.

Advanced neutron and [formula omitted]-ray shielding characteristics of nanostructured (90-x)Al-xGd2O3 composites reinforced by tungsten

This study introduces a composite material designed to offer exceptional mechanical strength and superior radiation shielding characteristics. By integrating tungsten into an aluminum Al-matrix with varying Gd2O3 content, we developed composites that meet the needful demands of mechanical durability and radiation protection in nuclear applications. The composites, synthesized via mechanical milling and sintering methods in planetary ball mills, have nominal compositions of (90-x)Al-xGd2O3 (x = 5, 10, 15 wt%) supplemented with 10 %W. The XRD analysis revealed phase structure transformations correlated with increased milling durations, while SEM-EDAX provided detailed morphological and elemental insights. TEM study confirmed a homogeneous distribution of nanocrystalline powders after 30 hours of milling while DSC thermographs indicated variations in thermal properties dependent on the Gd2O3 and tungsten content. The enhanced mechanical strength with higher concentrations of gadolinium and tungsten was characterized by Vickers microhardness tests. Neutron and γ-ray shielding properties were calculated using MCNP6.2 simulation code and Phy-X/PSD software. The thermal neutron macroscopic cross-section increased exponentially with higher Gd2O3 content, achieving values of 23.3 cm⁻¹ for 5 wt%, 48.4 cm⁻¹ for 10 wt%, and 73.7 cm⁻¹ for 15 wt%. Fast neutron removal cross-section also showed an increasing trend. The γ-ray linear attenuation coefficient decreased with increasing energy, but the Al-15Gd2O3-10 %W composite exhibited the highest LAC values, indicating superior γ-ray absorption capabilities. Correspondingly, the HVL values were lowest for the Al-15Gd2O3-10 %W composite. These findings demonstrate that Al-Gd2O3-W composites are promising materials for advanced industrial applications requiring robust mechanical properties and effective radiation shielding.

Role of MoO3 /ZnO substitutions on radiation shielding and mechanical characteristics of lead silicate glasses

In the composition range of x= 0-5 mol%, glasses in the system 60SiO2-35Pb3O4-(5 − 𝑥𝑥) ZnO-xMoO3 have been investigated. An amorphous network structure characterizes the glasses. The density values for the LZSM glasses scaled between 5.91 g/cm³ for Mo0 and 6.249 g/cm³ for Mo5. The ultrasonic technique indicates that the shear and longitudinal speeds (VT & VL) increase linearly as the amount of MoO3 substituted for ZnO in the fabricated glasses increases. The elastic moduli were calculated and found to be increased with an increase in both ultrasonic velocities and density of the glass, which suggests a correlation between these parameters in the fabricated glasses. The radiation attenuation capacity with the addition of MoO3 increased systematically, which indicates the role of MoO3 in modifying the glass composition and enhances its ability to attenuate against harmful radiation. Mo5 establishes excellent protective resources compared to other substances, so Mo5 develops a favorable selection for building radiation absorption blocks. Such blocks show an acute character in protecting both nature and a person's health versus the dangerous impacts of radiation exposure.

Assessing the shielding capability of NiO-infused BPSCCO ceramics against low-energy X-rays

This research examines the improvement of radiation shielding capabilities in Bismuth Strontium Calcium Copper Oxide (BSCCO) superconductors via NiO doping. With the increasing need for advanced shielding materials in high-risk areas, exploring effective and nonhazardous alternatives is becoming increasingly important. The purpose of the study was to investigate the radiation-shielding characteristics of BPSCCO superconducting ceramics and the effects of NiO additives on their shielding properties. Comparisons of linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), as well as fully simulated values for transmission factor (TF), neutron removal cross section (ΣR), electrical conductivity (Ceff), alpha and proton stopping powers, and radiation protection efficiency (RPE) using NIST XCOM, Phy-X, NIST Pstar and NIST Astar for all ceramic samples. The results indicate that optimal NiO doping notably enhances the radiation shielding capabilities of BSCCO ceramics, highlighting their significant potential for use in the medical, aerospace, and nuclear industries. This research provides a fundamental understanding of the potential of doped superconductor ceramics for radiation protection, promoting further research into these materials and the creation of safer, more efficient shielding solutions.

Examination of radiation shielding features of Bi2O3 modified Lithium Zinc Silicate glass system

In this study, several radiation shielding characteristics of Bi2O3 modified Lithium Zinc Silicate glass systems were reported using the Phy-X program. The mass attenuation coefficient (MAC) demonstrates a substantial energy dependency only at low energy range (0.284 MeV < E < 0.662 MeV), however it exhibits a slight energy dependency at high energies. It was shown that the transmission factor (TF) increases with energy, suggesting that at higher energies, more gamma rays can pass through the lithium zinc Silicate glasses. We reported the transmission factor (TF) at different thicknesses and we found that the TF at 0.347 MeV for Li25Bi0 varies between 0.92 and 0.77 for thicknesses of 0.3 and 0.9 cm respectively. Also, Li5Bi20's TF is lower than Li25Bi0's, which means that the effectiveness of the samples as shields will increase with the quantity of Bi2O3 present. The TVL is decreased by the introduction of Bi2O3, with Li5Bi20 possessing the smallest TVL and being regarded as the superior absorber. The lowest TVL recorded for selected glasses are 7.608, 3.189, 2.188, 1.677 and 1.427 cm for Li25Bi0 to Li5Bi20 respectively. The TVL results showed that at 0.284 MeV, the TVL for the Li25Bi0 is 5.33 times the TVL of Li5Bi20. At 0.347 MeV, the TVL of Li25Bi0 is 4.08 times the TVL of Li5Bi20, while at 0.662 MeV the TVL of Li25Bi0 is 2.36 times the TVL of Li5Bi20. We compared the effective atomic number (Zeff) for the selected glasses with other materials and we found that all these glasses have higher Zeff than ordinary concrete, and RS-253-G18, except Li25Bi0 sample which shows lower Zeff than RS-253-G18.

Elastic and radiation shielding properties of zinc borotellurite glass systems: The impact of gadolinium oxide

Using the formula [(TeO2)70(B2O3)30], this study examines the impact of Gd2O3 on the elasticity and radiation shielding characteristics of zinc borotellurite glass. Glass samples containing 1–5% mol% Gd2O3 were created by employing the melt quench technique. XRD verified that they are amorphous in nature, and the existence of TeO3, TeO4, BO3, and BO4 vibrational groups was revealed by infrared spectra. The structural alterations were shown by the range of longitudinal and shear ultrasonic velocities, which were 3908–4076 m/s and 2222–2277 m/s, respectively. The glass's rigidity was improved by the large rise in elastic moduli, such as bulk (45 GPa), longitudinal (80 GPa), shear (25 GPa), and Young's moduli (60 GPa), with a higher Gd2O3 content. Higher concentrations of Gd2O3 resulted in a rise in the mass attenuation coefficient (μρ), as measured by WinXcom, which enhanced gamma-ray shielding. The half-value layer (HVL) and mean free path (MFP) at 0.662 MeV decreased with increasing Gd2O3 in a consistent manner. The maximum density and optimum gamma-ray shielding performance were found in the glass containing 5 mol% Gd2O3. These results show Gd2O3 for applications needing greater rigidity and better radiation protection by demonstrating how it affects the elastic and radiation-shielding efficiency of the glass network.

Exploring the Radiation Shielding Efficiency of High-Density Aluminosilicate Glasses and Low-Calcium SCMs

A lot of work is now going into making low-calcium supplementary cementitious materials (SCMs) and aluminosilicate glasses so that they can be used as radiation shielding materials. These materials demonstrate superior performance in several aspects as compared to conventional concrete. The present investigation focuses on the radiation shielding characteristics of the evaluated materials, specifically their capacity to reduce the intensity of gamma rays and neutrons. Regarded for their exceptional density and ability to include heavy metal oxides, aluminosilicate glasses have remarkable shielding characteristics, especially when designed at the molecular scale. An evaluation of the performance of these materials in comparison to traditional concrete is carried out using Phy-X/PSD software. The goal is to determine the most important shielding properties, such as the mass attenuation coefficient, the linear attenuation coefficient, and the half-value layer. Our study findings suggest that some aluminosilicate glasses, such as GM, consistently demonstrate exceptional photon and neutron attenuation efficiency. The observation that GM performs better than other materials in tests like effective atomic number, rapid neutron removal cross section, and energy absorption accumulation factor supports this claim. There is evidence that using low-calcium glass-crystal materials (SCMs) with aluminosilicate glasses not only improves radiation protection but also makes solutions work better when space or weight are limited. The present investigation validates that these materials exhibit superior performance compared to conventional concrete in challenging environments such as nuclear waste storage, where safety is of utmost significance.

Effect of Sm2O3 on thermal, optical, mechanical, gamma and neutron shielding properties of zinc-boro-vanadate glasses

Abstract The effect of Sm2O3 on thermal, optical, mechanical, gamma and neutron shielding properties of newly prepared zinc borovanadate glasses has been investigated. Density is found increased and molar volume decreased with Sm2O3 content. The glass transition temperature ( T g ) , crystallization temperature ( T c ) and the peak crystallization temperature ( T P ) increased with increase of rare earth oxide content. These findings demonstrated an excellent glass-forming ability and thermal stability of the glasses. The optical properties have been explored through UV–vis spectroscopy. The indirect optical band gap energy ( E opt ) decreased from 2.978 to 2.679 eV, Urbach energy ( ∆ E ) increased from 0.273 to 0.299 eV and refractive index increased from 2.403 to 2.489 with increase in Sm2O3. Elastic moduli, Poisson’s ratio, Hardness and fractal bond connectivity were computed theoretically as per Makishima Mackenzie model. It is found that these glasses have appreciable mechanical strength and rigidity. Phy-X/PSD software has been used to determine different radiation shielding characteristics for the energy range 0.015–15 MeV. The mass and linear attenuation coefficients are found higher, and half value layer, tenth value layer and mean free paths are found lower than many radiation shielding glasses quoted in the literature values. The obtained Z eq values varied from 15.828–29.118 for energy range from 0.015 to 15 MeV, which are greater than those reported for several commercial glasses, concretes and rocks. Due to the Compton scattering process, exposure build up and energy absorption factor are found to be highest in the medium energy region. The fast neutron removal cross-sections of the glasses are observed to be significantly high. For the first time, thermally stable and mechanically strong zinc borovanadate glasses mixed with Sm2O3 have been thoroughly investigated for various properties and concluded that these glasses are suitable for optoelectronics and γ-shielding applications.

Radiation Shielding Characteristics and Transmission Factor values of some Selected Alloys: A Monte Carlo-Based Study

Radiation Shielding Characteristics and Transmission Factor values of some Selected Alloys: A Monte Carlo-Based Study

Influence of ZnO variation on glass characteristics: Physical, mechanical properties and radiation shielding

This study examines the effects of different ZnO concentrations on the mechanical and radiation shielding characteristics of a glass series that is fabricated using the melt quenching method, where x = 0, 10, 20, and 30 mol.% and the chemical formula is (75-x) B2O3+15Na2O+5CuO+(5 + x) ZnO. The physical and mechanical properties of the prepared glass samples were investigated, where the increase in ZnO concentration between 5.00 mol.% and 35.00 mol.% increases the prepared glass density between 2.319 and 3.032 mol.%, respectively. Additionally, the Makishima-Makinze model was used to examine the mechanical properties of prepared glass samples. The elastic moduli reduced with increasing the substitution of B2O3 by ZnO, where the increase in ZnO concentration between 5.00 mol.% and 35.00 wt% reduces the micro-hardness between 5.279 and 4.578 GPa. Furthermore, the NaI (Tl) detector was used to examine the radiation shielding properties of prepared glass samples. The measurements show an enhancement in the linear attenuation coefficient of prepared glass samples with increasing the ZnO content, where the increase in the ZnO concentration between 5.00 and 35.00 mol.% increases the linear attenuation coefficient by 29.927 %, 25.919 %, 30.917 %, 34.529 %, and 43.942 %, respectively at gamma-ray energies of 0.511, 0.662, 1.173, 1.275, and 1.332 MeV.The increase in the linear attenuation coefficient enhances the radiation protection efficiency of prepared samples and decreases the half-value layer for the prepared glass samples.

The impact of V2O5 on structure, dielectric, and radiation-shielding characteristics of borate-lead-fluoride glasses

The impact of V2O5 on structure, dielectric, and radiation-shielding characteristics of borate-lead-fluoride glasses

Optical and gamma-ray shielding properties of calcium sodium borate glasses with varied equal concentrations of ZnO and BaO

This study presents the optical and radiation shielding characteristics of a newly developed borate glass, doped with equal quantities of ZnO and BaO, and modified with calcium and sodium. The glass samples were prepared using the melt quenching technique, with the composition formula (80-x-y)B2O3-10CaO-10Na2O-xZnO-yBaO, where x and y were varied at 5, 10, 15, and 20 mol%. Comprehensive analyses of the optical and gamma shielding properties were carried out using UV–visible spectrophotometry and Phy-X software, respectively. The UV–visible spectroscopic data allowed for the calculation of various parameters including the direct and indirect optical energy band gaps, refractive index, dielectric constants, and polarizability. It was observed that the direct optical energy band gap decreased from 3.91 to 3.10 eV, while the indirect band gap fell from 3.41 to 2.91 eV with increasing ZnO and BaO content. Conversely, the refractive index rose from 2.29 to 2.42 with higher concentrations of ZnO and BaO. The linear attenuation coefficients (LACs) across the range of 0.015–15 MeV exhibited an inverse relationship. Among the glass samples, B40Zn20Ba20 exhibited the lowest tenth value layer (TVL) and the highest effective atomic number (Zeff), indicating its superior performance as a radiation shielding material. Overall, the produced glass samples demonstrate commendable properties for both optical applications and radiation shielding.

Optimization of structure, optical, magnetic, and radiation shielding properties of ZnO@xSrFe12O19 nanocomposites

In this work, the pristine ZnO, SrFe12O19 (SFO), and their nanocomposites (ZnO/x SFO: x = 1, 3 and 5%) were synthesized by co-precipitation and sonomechanical method. The x-ray diffraction data validate the preparation of ZnO, SFO, and nanocomposite samples with high phase purity. The optical band gap was calculated from UV–vis-NIR diffuse reflectance measurements, and it was modified by increasing SFO content. Adding 1, 3, and 5 wt% of SFO to the ZnO matrix showed ferromagnetic characteristics for the nanocomposites with a squareness ratio of around 0.49, which considered these nanocomposites as a magnetic semiconductor suitable for digital memory and spintronic applications. Additionally, the radiation shielding features of the prepared samples were evaluated. The shielding parameters for the studied samples were obtained using the Phy-X/PSD program. The fast neutron removal cross-section of SFO was 0.094 cm−1, the highest among the investigated samples, while the composites had similar values, about 0.083 cm−1. The results indicated that the γ--ray attenuation ability and the values of exposure buildup factor for the prepared samples were close. Therefore, ZnO, SFO, and their nanocomposites compared to stationary shielding materials (SMs), can be candidates for applications where radiation protection is needed.

Radiation Shielding Analysis of Multi-Component Glasses: Effects of Varying BaO, PbO2 and Gd2O3 Concentrations

This work investigates the impact of BaO, PbO2, and Gd2O3 on newly developed borate glasses’ radiation shielding characteristics. The transmission factor (TF) of the glasses is almost zero at the low energy of 0.0395 MeV, which indicates favorable low-energy photon shielding. The maximum TF is reported at 1.46 MeV for the free Gd2O3 glass sample, ranging from 0.89 (0.5 cm thickness) to 0.73 (1.5 cm thickness). Moreover, with more BaO, PbO2, and Gd2O3 content added to the glasses, the TF decreases, indicating an enhancement in the efficiency of the glasses’ radiation protection with the introduction of BaO, PbO2, and Gd2O3. There is a 4.309 to 5.068 g cm−3 increase in the glasses’ density, and, as a result, the mean free path decreases, suggesting improved performance for radiation protection with the adding of more BaO, PbO2, and Gd2O3 contents to the glasses. At 0.122 MeV, the free Gd2O3 glass’s half value layer value is 0.098 cm, while the tenth value layer is 0.325 cm.

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.

Influence of waste glass on the gamma-ray shielding performance of concrete

In this work, the local low-cost materials from Nigeria were companied together to produce a lead-free concrete that can be used in shielding the ionizing γ-rays. This work investigated the impacts of partially replacing coarse aggregates (crushed granite) with a crushed waste glass on the chemical, physical, and radiation shielding characteristics. The developed concretes’ density was measured experimentally, and the fabricated concretes’ elemental chemical composition was determined utilizing a Thermo-Scientific X-ray fluorescence connected to an ARL-QUANT’X-EDXRF-Analyzer. The increase in the waste glass/granite (WG/G) substitution ratio between 0 and 17.6 % decreases the density of the produced concrete from 2.4 g/cm3 to 2.33 g/cm3. On the other hand, the absorption per unit mass (MAC) of the produced concretes increased by raising the WG/G ratio, where there was a 0.217–0.247 cm2/g increase in the MAC at 0.081 MeV, by raising the WG/G ratio between 0 and 17.6 %. Simultaneously, the study shows that the radiation protection efficiency (RPE) at 2.506 MeV for a 10 cm thickness of the fabricated concrete reaches 53.49, 61.14, 54.98, and 55.29 % for concretes with WG/G content of 0.0, 5.3, 11.1, and 17.6 % with the same order, respectively. Therefore, the thicker thicknesses of the developed concretes can offer high shielding capacity to be applied in radiation protection applications.

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.

The effect of rare earths (Nd3+, Er3+, Yb3+) additives on the radiation shielding properties of the tungsten oxide modified tellurite glasses

Abstract In this study, we have reported on the effect of the rare earth oxides on the radiation protection performance of the tellurite glasses. In order to determine the effect of rare earth oxides on the radiation shielding properties of tungsten oxide (WO3) modified tellurite glasses, three rare earth element oxides (Nd2O3, Yb2O3, and Er2O3) have been selected. The glass systems have been synthesized using the traditional melt quenching method and were doped with the different amount (1 %, 3 %, 5 %) of the oxides of rare earth elements (Nd2O3, Yb2O3, Er2O3). The linear attenuation coefficient, mass attenuation coefficient, half value layer, and effective atomic number of the synthesized samples were experimentally measured for 662, 1,173 and 1,332 keV gamma-ray energies which were emitted from 137Cs and 60Co radioactive sources. Measurements were conducted in narrow beam transmission geometry using a NaI(Tl) scintillation detector. In addition, all these parameters were calculated theoretically using the WinXCOM program in the energy region of 0.015–15 MeV. The addition of different types and amounts of rare earth oxides to the tellurite glass system was found to significantly enhance the radiation protection performance of the glasses. In particular, it was found that the radiation shielding characteristics of the glasses improved with increasing amount of rare earth doping, the TWYb5 glass system had the best radiation shielding properties, and there was a trend among the doped rare earth oxides in the form of Yb &gt; Er &gt; Nd according to their radiation shielding performance.