Radiation Shielding Effectiveness Research Articles

Tailoring perovskite ceramics for improved structure, vibrational behaviors and radiation protection: The role of lanthanum in PbTiO3

This study investigates the characteristics of lanthanum (La)-doped lead titanate (PbLaxTi(1-3x/4)O3 where, x = 0.0, 0.02, 0.04, 0.06, 0.08, and 0.1), a type of perovskite ceramic. It specifically focuses on analyzing its structure, vibrational properties, and efficacy in shielding against radiation. The prepared samples are investigated by X-ray diffraction (XRD), which clarified that the small doping of La (x ≤ 0.06) produced the required phase, and increasing the La doping (x > 0.06) produced nonrequired phases (secondary phase). Also, increasing the La doping converted the crystal symmetry from tetragonal to cubic, which was confirmed by the tetragonality raio (c/a) calculations. Also, the samples are investigated by Fourier transform infrared (FTIR) spectroscopy to confirm the XRD results. Transmission electron microscopy (TEM) examination clarified that the prepared samples were in the nanoscale range with a maximum crystallite size value of around 70 nm. In addition, the shielding effectiveness of all the prepared samples was theoretically evaluated using the Phy-X/PDS program by considering characteristics such as the linear attenuation coefficient (GLAC), mean free path (GMFP), transmission factor (TF), and radiation protection efficiency (RPE). Increasing the La concentration increases the theoretical density to 4.98 gm/cm3 at x = 0.1, leading to low TF and GMFP values and high GLAC values. This produces samples with high attenuation to radiation and high shielding effectiveness.

Impact of Bi2O3 on the glass system B2O3 -TeO2–MgO–PbO on the purpose of radiation shielding efficacy

In this study, eight glass samples were prepared with the composition of [x Bi2O3-(75-x) B2O3–15TeO2 –5MgO–5PbO; where x = 0, 10, 20, 25, 30, 40, 50, and 60 mol%]. In the composition of those glass samples, various amountsof B2O3 were replaced by Bi2O3 to improve the glass material's radiation shielding capability. The mechanical properties of these glasses have been evaluated using densimeter and microhardness. The Vickers microhardness (Hv) slightly decreases as the amount of Bi2O3 increases due to the formation of Non-Bridging Oxygen (NBO). To evaluate the radiation shielding effectiveness of the prepared glass samples, we performed Monte Carlo simulations of several shielding parameters. The mass attenuation coefficients of the experimentally produced BTMPBi glass series were calculated using NIST and MCNP6, and reasonable agreement was found between the simulation and experimental results. The relative difference between NIST and MCNP6-based results was calculated, and the maximum deviation was 2.21% for the 1173 keV gamma ray incident in the BTMPBi60 glass sample. The value of the mean free path of those prepared glass samples maintained the following trend - BTMPBi0> BTMPBi10> BTMPBi20> BTMPBi25> BTMPBi30> BTMPBi40> BTMPBi50>BTMPBi60. The prepared glass sample BTMPBi0 showed a 2.6 times higher value of the mean free path at energy 1332 KeV compared with the prepared BTMPBi60. Analyzing the composition of the prepared glass samples, it is clear that the greater the amount of Bi2O3 the greater the value of linear attenuation coefficient (LAC) and effective atomic number. Based on the results, it can be concluded that the glass sample containing 60 mol % of Bi2O3 (BTMPBi60) exhibited the highest radiation shielding capability among all of the prepared samples.

Thermal, and radiation shielding properties of SrO–B2O3–TeO2–ZnO–Bi2O3 glasses doped with Dy2O3

The newly proposed materials demonstrated outstanding and effective radiation shielding capabilities and promising mechanical properties. A series of (20-x) SrO-(73)B2O3-(5)TeO2-(1)ZnO-(1)Bi2O3 doped with x-Dy2O3 have been produced employing the traditional melt-quench process, with the concentration of Dy2O3 varying from 0.05 to 1.5 mol%. This research examined glass samples' structural stability, mechanical and thermal characteristics, and radiation shielding capabilities. All of the glasses were amorphous, as confirmed by the X-ray examination, and the glass with the label SBTZBD6 had the maximum density because of the higher Dy2O3 content. The insert of Dy2O3 into the glass composition increased density values from 2.94 to 3.04 g/cm3 for SBTZBD1 and SBTZBD6 and improved mechanical properties such as Poisson ratio and elastic moduli. The hardness Vickers showed the maximum value at 1095.7 HV corresponding to Dy2O3 1 mol%, indicating the influence of Dy2O3 addition on the mechanical properties. The ability of the generated samples to shield against several forms of radiation, such as alpha, proton, neutron, and gamma radiation, was examined using SRIM and Phy-X software. The lowest HVL is 0.009 cm for SBTZBD6 at 0.02 MeV, the highest HVL was observed at 15 MeV with a value equal to 7.066 cm for the same sample. Dy2O3 was used instead of SrO, significantly increasing the μ/ρ values and improving radiation shielding. However, it was discovered that fast neutron shielding experienced a reduction in energy loss per unit mass (mass stopping power) when SrO was replaced with Dy2O3. However, the substitution also reduced energy loss per unit mass for alpha and protons and fast neutron shielding. To sum up, this study's glass samples are highly recommended for ionizing radiation shielding.

X-ray radiation shielding: Enhanced performance with BaCO3 nanocrystal-infused composite polyester/PVA/BaCO3 exhibiting medicine capsule-like structure

The advanced technology for effective X-ray radiation shielding is increasingly important. The use of new materials and innovative strategies has the potential to revolutionize radiation shielding, making it safer due to its outstanding characteristics. Herein, the effect of using nanocrystals of BaCO3 in a composite polyester/PVA/BaCO3 with medicine capsule-like structure are reported. Our findings showed that the BCO60 composite had an excellent shielding characteristic, it was able to attenuate half of the incoming photon energy for only 0.028 cm form their thickness. We compared our experimental findings to theoretical values through the Phy-X/PSD online software and show a very good match. The medicine capsule-like environmentally inspired X-ray radiation shield provides new strategies for design and preparation X-ray radiation shielding in the future.

Influence of titanium dioxide doping on the attenuation and optical characteristics of magnesium borate glass systems

This research examines the effects of varying titanium oxide (TiO2) concentrations in glass formulations, denoted as [(53-x)B2O3–7MgO–20BaF2–20Na2O-xTiO2] or BMBNTix, where x varies from 0 to 8 mol% in 2 % increments, on optical properties and radiation shielding effectiveness. Using MCNP5 (MC) Monte Carlo simulations and Phy-X software, this study assesses a range of photon energies from 0.015 to 15 MeV, focusing on key radiation shielding metrics such as the linear attenuation coefficient (μ), the half-value layer (HVL), and the tenth value layer (TVL). The results reveal a clear relationship between increased TiO2 levels in the BMBNTix glasses and improved radiation shielding performance. Notably, the linear attenuation coefficient (μ) steadily climbs from BMBNTi0 to BMBNTi8, highlighting the beneficial effect of a TiO2 addition to the material's ability to attenuate radiation. This trend is inversely mirrored in HVL values, which decrease from 0.010 cm for BMBNTi0 to 7.646 cm for BMBNTi8, reflecting enhanced shielding efficiency over the entire studied photon energy range. The effective atomic number (Zeff) also showcases a dynamic range from 40.793 to 15.101, suggesting a complex relationship between TiO2 content and photon interaction. Moreover, the study indicates a slight but consistent increase in the fast neutron removal cross-section (ΣR) from 0.104 cm−1 for BMBNTi0 to 0.106 cm−1 for BMBNTi8, pointing to improved neutron shielding with greater Ti and oxygen content in the glass. These insights highlight the potential of TiO2-enriched magnesium borate glasses as superior options for effective photon and neutron shielding, particularly in nuclear medicine, emphasizing their role in enhancing radiation safety measures.

Analysis of structural, optical, mechanical properties and evaluation of radiation shielding effectiveness of strontium borate glasses doped with ZnO nanoparticles

This research meticulously explores the synthesis, structural, thermal and optical characterization of zinc oxide nanoparticles (NPs) infused strontium borate glasses (termed SZ glasses) and their applicability as radiation shielding. The glasses have been produced using the melt quenching process in the composition series of (60-x)B2O3: xZnO: 10SrO: 10Na2O: 10CaO: 10BaO, where x varied from 0 to 20 % mol. In order to dope ZnO into glasses, its structural and morphological characteristics were investigated after it was synthesized by solution combustion method. It was found that the inclusion of ZnO significantly impacted the glasses' density, molar volume, hardness, yield stress, and thermal stability. The optical properties of the produced glasses, such as transmittance, reflection, transparency, opacity and band gap energies, were examined and the effect of ZnO on the optical properties of the glasses was investigated. Crucially, the SZ glasses exhibited notable efficiency in shielding against gamma photons and fast neutrons. This is evidenced by the favourable change in the mass attenuation coefficients with increasing ZnO concentration. Parameters like the half-value layer, effective atomic number, and energy absorption buildup factors were calculated to gauge the radiation attenuation proficiency of the SZ glasses, demonstrating their potential utility in radiation protection. In conclusion, the developed SZ glasses display advantageous structural, thermal, and optical qualities, along with robust shielding capabilities against gamma photons and fast neutrons. This study contributes significant knowledge to the field of novel glass materials, paving the way for their application in various industrial and medical contexts requiring radiation shielding.

Architectural approach for evaluation of radiation shielding integration in space habitats

NASA HRP considers developing radiation protection for human space flight and surface habitation as one of the critical technologies for successful deep space exploration. Although the danger of radiation exposure is recognized as a potential show-stopper for deep space exploration, and radiation effects on humans are now understood better than before, shielding strategies for different stages of space flight and habitation are still not addressed in a fully comprehensive manner. Habitats and all space structures planning and design are guided by essential requirements and constraints associated with safety, manufacturing and assembly procedures, propellant and construction costs, maintenance, crew and/or passenger satisfaction. This paper reviews radiation shielding options for space habitats and discusses their feasibility in relation to habitability needs, including the potential for outside viewing in distinct types of space habitats. Typically, radiation protection depends on the thickness of the exterior structure that consists of a pressurized shell, multilayer insulation (MLI) and any applied radiation shielding material. The mass of the external protection shell is the primary factor of radiation shielding effectiveness. Nevertheless, using materials with low atomic numbers (e.g., Boron (5), Carbon (6), and H2O) helps to lower secondary radiation hazards. Water, which is rich in hydrogen and has the lowest atomic number, can also be used for other mission needs. Other materials, including biomaterials, can be considered when their inclusion in the structure is possible and appropriate. The paper presents a comprehensive strategy for radiation shielding selection that includes investigation of complications associated with a type of space habitat structure, mission needs, duration, destination, and crew requirements. The approach presented in the paper aims to establish an evaluation methodology for defining the feasibility of the integration of diverse radiation shielding types into habitat structures. The paper summarizes by reviewing radiation shielding proposals with selected case studies including water, regolith, hydrogen-rich polymers, biotechnology, polyethylene/boron nitride composites, and active strategies.

Cadmium-modified iron lead borate glasses for radiation protection

Using cadmium-modified iron lead borate glasses with formula 30 B2O3 – 40 PbO – 10 Na2O – (20 -x) Fe2O3 – x CdO where x ranges from 0 to 20 mol%, this work aims to investigate the structural, physical, elastic, and radiation-shielding properties of practical economic radiation shields. The X-ray diffraction patterns confirm the amorphous nature of the samples. The results of Fourier-transform infrared spectroscopy (FTIR) demonstrate the formation of robust B–O–Cd linkages and diborocadmium ([B2CdO8]2−) structures, as well as the conversion from [BO3] to [BO4] structural units with increased CdO and the presence of PbO and Na2O as modifiers. The CdO function also plays a dual role as a former and as a modifier. The FTIR analysis showed that the material's elasticity and the CdO oxide concentration were directly correlated, suggesting that the glass system becomes stiffer as the CdO concentration increases. The study explores the effectiveness of radiation shielding and demonstrates that CdO-rich samples have higher effective atomic numbers and attenuation qualities.

Optimization optical and radiation shielding properties via controlling the Hirshfeld topological constraints: A case study of carbonate-based crystals

This work explores the potential of carbonate-based ceramics (CBC) as materials for optical and radiation shielding applications. The results reveal the distinctive behavior of various CBC materials in shielding γ-rays. At an intermediate energy of E = 0.5 MeV, SiO2 has a MAC value of 0.087, whereas the MAC values for the CBCs are as follows: (CMs, MAC (g/cm2)): (CaCO3, 0.088), (MgCO3, 0.087), (SrCO3, 0.086), (BaCO3, 0.096), (ZnCO3, 0.086), (CdCO3, 0.091), and (PbCO3, 0.145). Also, the effective atomic numbers (Zeff) found to range from 11.03 to 78.82. These values surpass those of silicon dioxide (SiO2), highlighting the superior γ-ray attenuation capabilities of CBC. The work also delves also into the optical properties of CBC materials, highlighting the interplay between density (2.61 < ρ < 6.72 g/cm3), band gap energy (2.680<Eg < 5.050 eV), and refractive index (1.99254 < n < 2.48905). Furthermore, the study delves into the impact of charge density within Hirshfeld voids on these properties, revealing that as the interatomic interactions increase: 2.1% < O⋯C<26.8%, 9.3% < O⋯O<26.3%, or 63.3% < O … A2⁺<86.4% (A = Ca, Mg, Sr, Ba, Zn, Cd) due to higher charge density, thus the LAC and n values may tune among the studied CBC. The fine-tuning of topological and charge density distributions within the crystal's voids offers a promising avenue to optimize these materials for enhanced radiation shielding effectiveness or optical properties. This interplay between crystal structure, composition, charge distribution, Hirshfeld topological constraints as key factors in determining their radiation attenuation and optical capabilities was explored.

Enhancing radiation shielding effectiveness: a comparative study of barium-doped tellurite glasses for gamma and neutron radiation protection

This study investigated the radiation shielding performance of the xBaO-(30-x)TeO2-35Bi2O3-35B2O3 glass system, where x = 5, 10, 15, 20 and 25, using Phy-X/PSD software and MCNPX Monte Carlo code. Key radiation shielding indicators, including attenuation coefficients, half value layer (HVL), tenth value layer (TVL), effective atomic number (Zeff), mean free path (MFP), and build-up factors, were measured within the energy range of 0.015–15 MeV. Further, the study assessed the glasses' capacity to block fast neutrons, using the fast neutron removal cross-section (ΣR) as a metric. The results showed that gamma shielding effectiveness follows the order: BaTBiB-1 < BaTBiB-2 < BaTBiB-3 < BaTBiB-4 < BaTBiB-5 at all photon energies. Additionally, the ΣR values for BaTBiB-1 to BaTBiB-5 glasses were 0.10179, 0.10263, 0.10362, 0.10581, and 0.10623 cm−1, respectively. Therefore, the findings demonstrate that including BaO enhances the gamma and neutron shielding characteristics of tellurite glasses, making them valuable for radiation-related applications.

The Hirshfeld topological surfaces, volumes, and their voids charge density interplay on radiation shielding properties: A case study of carbide-based ceramics

Transition metal carbides (TMCs) are explored for their potential as radiation shielding materials, with a focus on their γ-ray attenuation properties. These high-density materials, including WC, TaC, HfC, NbC, and VC, are evaluated across an energy range of 0.015–15.0 MeV. Notably, at low incoming photon energy (0.0150 MeV), these TMCs exhibit mass attenuation coefficients (MAC) (TMC, MAC (g/cm2)): (WC, 130.417), (TaC, 125.730), (HfC, 120.873), (NbC, 23.751), and (VC, 32.377) and effective atomic numbers (Zeff) from 22.69 to 73.68. These values surpass those of silicon dioxide (SiO2), highlighting the superior γ-ray attenuation capabilities of TMCs. TMCs exhibit a distinct trend in MAC values, with tungsten carbide (WC) consistently demonstrating the highest MAC values, making it the most efficient γ-ray attenuator. Hafnium carbide (HfC) closely follows, with tantalum carbide (TaC) exhibiting lower MAC values, while niobium carbide (NbC) and vanadium carbide (VC) display the lowest values. These differences can be attributed to variations in material composition and structure. Furthermore, the study delves into the impact of charge density within Hirshfeld voids on LAC values, revealing that as X⁴⁺ … C interactions increase due to higher charge density, LAC values rise. This fine-tuning of topological and charge density distributions within the crystal's voids offers a promising avenue to optimize these materials for enhanced radiation shielding effectiveness. Overall, this research contributes to the understanding of the potential utility of TMCs in radiation shielding applications, showcasing the interplay between crystal structure, composition, and charge distribution as key factors in determining their radiation attenuation capabilities.

Nuclear radiation shielding performance of the new lead‐free TeO2–Bi2O3–ZnO–BaF2 glass

AbstractThis paper studied the radiation shielding properties of new lead‐free telluride glass with different BaF2 content. The 65TeO2–15Bi2O3–(20 − x)ZnO–xBaF2 glass systems (where x = 1, 3, 5, 7, 9 mol%) were tested through the X‐ray diffraction, ultraviolet–visible spectrophotometer, and differential scanning calorimetry. The glass system exhibited good thermal stability and a uniform surface without surface crystallization. The linear attenuation coefficient of the TBZBF series glass was tested using five different gamma radiation sources (241Am, 133Ba, 57Co, 137Cs, and 60Co). They were calculated to the mass attenuation coefficient, half‐value layer, mean free path, and effective atomic number through numerical simulations with XCOM software. The maximum mass attenuation coefficient for TBZBF‐9 was calculated to be 5.3577 cm2/g. Comparisons were made between this glass system and other tellurite and leaded glasses reported in the literature. The glass system exhibited superior radiation shielding capability compared to leaded tellurite glass under the same testing conditions. The gamma radiation shielding capacity increased with BaF2 content in the glass system. These results show that TBZBF‐9 exhibited the best gamma radiation shielding effectiveness while maintaining glass transparency.

Development of a flexible composite based on vulcanized silicon casting with bismuth oxide and characterization of its radiation shielding effectiveness in diagnostic X-ray energy range and medium gamma-ray energies

The study aims to develop a novel, lead-free, flexible and lightweight composite shielding material against ionizing radiation. For this, it was used bismuth oxide (Bi2O3) in RTV-2 silicon matrix. The shielding tests were carried out in both diagnostic X-ray energies and intermediate gamma-ray energy range of up to 662 keV to determine the radiation attenuation properties of this material in terms of attenuation ratio, half value layer, tenth value layer, mean free path and lead equivalency of samples in weight of 30%, 40%, 50% in Bi2O3. In the diagnostic X-ray energy range, half value layer, tenth value layer and lead equivalency (in mm Pb) of the produced samples were measured at 80 and 100 kVp narrow beam conditions according to the requirements of EN IEC 61331-1 standard. The results show that lead equivalent values of the produced novel sheets was measured to be 0.16 mm Pb, corresponding to a 6 mm thickness of the flexible sample when it contains 30% wt. Bi2O3 in RTV matrix. The experimental findings for durability and flexibility also indicated that this new RTV-based flexible, lead -free shielding composite can be used safely for especially for manufacturing aprons, garments and thyroid guards used in mammography, radiology, nuclear medicine and dental applications in practice.

Recent Advances and Challenges in Polymer-Based Materials for Space Radiation Shielding.

Space exploration requires the use of suitable materials to protect astronauts and structures from the hazardous effects of radiation, in particular, ionizing radiation, which is ubiquitous in the hostile space environment. In this scenario, polymer-based materials and composites play a crucial role in achieving effective radiation shielding while providing low-weight and tailored mechanical properties to spacecraft components. This work provides an overview of the latest developments and challenges in polymer-based materials designed for radiation-shielding applications in space. Recent advances in terms of both experimental and numerical studies are discussed. Different approaches to enhancing the radiation-shielding performance are reported, such as integrating various types of nanofillers within polymer matrices and optimizing the materials design. Furthermore, this review explores the challenges in developing multifunctional materials that are able to provide radiation protection. By summarizing the state-of-the-art research and identifying emerging trends, this review aims to contribute to the ongoing efforts to identify polymer materials and composites that are most useful to protect human health and spacecraft performance in the harsh radiation conditions that are typically found during missions in space.

Calculation of The Effects of Fly Ash in Concrete Samples Used as Construction Materials on Radiation Shielding Efficiency Using EGS4 Code

The aim of this study is to determine the effects of reducing cement and replacing it with fly ash in concrete samples used as construction materials on the radiation shielding efficiency. The radiation shielding effect of concrete samples was determined using the EGS4 code. By contrasting the outcomes with XCOM data, theoretical discussion was conducted. At gamma ray energies between 59.5 and 1332 keV, the mass attenuation coefficients (μ/ρ) of concrete samples mixed with fly ash were theoretically investigated using WinXCOM and EGS4. Then, several shielding parameters, including mean free path (MFP), half value layer (HVL), radiation protection efficiency (RPE), effective atomic number (Zeff), and gamma-ray kerma coefficients (kγ), were found using the mass attenuation coefficients. It has been noted that the parameters governing radiation shielding performance of concrete samples used as building materials are altered when cement is reduced and fly ash is substituted.

Comparative study of dose for different fluence of neutron

The comparative study aims to investigate the dose received by materials exposed to different fluence of neutron radiation. The research is significant in the field of nuclear energy and radiation protection, as neutron radiation is one of the most common types of radiation produced by nuclear reactions. In this study, various materials are exposed to different fluence of neutron radiation, and the dose received by each material was measured using dosimeters. The results showed that the dose received by the materials increased with increasing fluence of neutron radiation. Furthermore, the study found that the dose-response relationship different between different materials, highlighting the importance of material selection in radiation protection. The study concludes that a better understanding of the dose-response relationship for different materials can help in the development of more effective radiation shielding materials and improve radiation safety in various applications.

Enhancement of optical and radiation shielding properties in calcium–magnesium silicate bioactive glasses through Na2O and P2O5 additives

The present study investigates the influence of Na2O/MgO and P2O5/SiO2 substitutions on the structure and protective properties of bioactive glasses composed of 32CaO–19MgO–0.5P2O5–0.5CaF2–48SiO2 (mole %). The glass samples are prepared using the conventional melt-quenching method. Optical analyses, including refractive index (n), molar refraction (Rm), and cationic polarizability (αm), are calculated and discussed to examine structural modifications. Raman spectroscopy is employed for detailed structural analysis. The effects of compositional changes on the protective parameters are thoroughly investigated by theoretically determining mass attenuation using the newly developed Phy-X/PSD software and XCOM programs, which are then experimentally confirmed at three selected radioactive isotope energies. Experimental measurements of mass attenuation coefficient follow the sequence: MACG1 > MACG2 > MACG3 > MACG4. Raman spectroscopy results indicate that the glass network primarily consists of silicate and phosphate species as the main structural units. An increase in the molar ratio of Na2O and P2O5 improves the radiation shielding effectiveness of the samples. Among them, sample G5, with the lowest SiO2 and MgO content, exhibits the best shielding characteristics due to its high density and molar fraction of Na2O and P2O5. A correlation between microhardness and protective effectiveness is also established. The obtained results support the potential use of these glasses as dual agents for both radiation shielding and medical devices simultaneously.

Measurement on the neutron and gamma radiation shielding performance of boron-doped titanium alloy Ti50Cu30Zr15B5 via arc melting technique

The significance of radiation shielding is on the rise due to the expanding areas exposed to radiation emissions. Consequently, there is a critical need to develop metal alloys and composites that exhibit excellent capabilities in absorbing neutron and gamma rays for effective radiation shielding. Low-density Ti-based alloys with controlled structural properties can be used for radiation protection purposes. The present research investigates boron-doped Ti-based alloy, Ti50Cu30Zr15B5, which is synthesized by arc melting technique, and its structural, mechanical properties, neutron, and gamma-ray transmission rate were investigated. Monte Carlo N-Particle simulation (MCNP6.2) code is used for calculating the Thermal (2.53 × 10−8 MeV) and fast (2 MeV) neutron transmission ratio (I/I0) dependent on the sample thickness. The Phy-x program is employed for calculating the gamma-ray LAC, MAC, HVL, TVL, and MFP values. The calculated neutron shielding performance parameters of Ti50Cu30Zr15B5 alloy were compared with materials in the literature. It was found that Ti50Cu30Zr15B5 alloy demonstrated impressive physical characteristics, suggesting that it can serve as a promising alloy for neutron and gamma-ray shielding applications.

Impact of micro/nano cadmium oxide on shielding properties of cement–ball clay matrix

This study investigates the gamma radiation shielding properties of cement–ball clay matrix composites doped with micro- and nano-sized cadmium oxide (CdO) particles. The linear attenuation coefficient (LAC) was determined using a sodium iodide (NaI) detector and five radioactive point sources with energies ranging from 59.5 to 1408 keV. The LAC values obtained were compared to the XCOM database and found to be in good agreement. The composites' half-value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Zeff), equivalent atomic number (Zeq), and absorption buildup factor (EABF) were determined. The results showed that the addition of CdO particles improved the radiation-shielding behavior of the composites and increasing the weight fraction of CdO particles increased the shielding effectiveness. The results also illustrated that when nano-sized CdO particles were compared to their micro-sized counterparts, there was a significant enhancement in radiation shielding effectiveness. For instance, a composite material composed of 50% cement, 41.7% ball clay, and 3.8% nano CdO at an energy level of 0.0595 MeV exhibited a remarkable 12.2% increase in attenuation, surpassing the performance of the micro-sized sample with an equivalent concentration. Similarly, another composite consisting of 50% cement, 33.3% ball clay, and 16.7% nano CdO demonstrated a significant 15.4% increase in attenuation at the same energy level, when compared to the micro-sized sample. The study demonstrates the potential of CdO-doped cement–ball clay matrix composites for gamma radiation shielding applications.

Impact of PbO on structural, thermal, optical and gamma ray shielding behaviour of TeO2-CdO based glasses

A study was conducted to investigate the effect of an increase in the concentration of PbO on the structural, thermal, optical, and gamma ray shielding behavior of TeO2-CdO based glasses. The glasses were found to contain TeO4 and TeO3 units, as well as CdO metal oxide clusters, as indicated by the Raman spectrum. The glasses displayed minor weight loss (approximately 3%), suggesting high resistance to thermal degradation. With an increase in the concentration of PbO, the glass transition temperature (Tg), onset temperature (To), and crystallization temperature (Tc) all decreased. Additionally, the indirect band gap energy decreased from 3.497–3.337 eV as the lead oxide concentration increased. Moreover, the effects of PbO concentration on the linear attenuation coefficient (LAC) were investigated. The LAC values were found to be highest at 39.5 keV and decreased with increasing energy. As the PbO concentration increased, LAC values also increase. The Zeff displayed an inverse relationship with energy, except for an abrupt increase at 121.8 keV. The half value layer was found to be positively correlated with energy and varied with changes in PbO and CdO concentrations. The glasses demonstrated effective gamma radiation shielding properties, with the HVL remaining small even at higher energies, suggesting potential applications in industries such as medical imaging where thin shielding materials are preferred.