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Many oxide additives have historically been used to enhance the radiation shielding properties of glasses, yet the potential of high-entropy oxides (HEOs), which have gained popularity in material science for their unique properties, has not been explored in this context. This study is the first to investigate the radiation shielding capabilities of Zinc-Tellurite glass infused with High Entropy Oxide (HEO), specifically utilizing the novel attributes of a synthesized TiZrNbHfTa. In this study, the nuclear shielding properties of newly fabricated Zinc-Tellurite glasses doped with TiZrNbHfTaO x with a composition (25ZnO·75TeO 2)100-x. (TiZrNbHfTaO x)x (x = 0, 1, 2, 3, 4 mol%) were studied. Through the synthesis of a TiZrNbHfTa HEA and its integration into glass structure, we have developed a series of novel materials with enhanced protective properties against both gamma-ray and neutron radiation. Experimental results demonstrate that the HEO-infused glass, particularly the HEC1-4 composition, significantly surpasses traditional shielding materials in neutron attenuation, evidenced by its superior effective neutron removal cross-section. Additionally, the HEC1-4 glass demonstrates improved gamma-ray shielding capabilities, with increased mass attenuation coefficients and decreased half-value layers, indicating a higher capacity for photon interaction and absorption. It can be concluded that the incorporation of High Entropy Alloys into glass matrices not only opens a new frontier in radiation shielding materials but also provides a versatile and effective solution with considerable potential for enhancing safety measures in radiation-prone environments. [ABSTRACT FROM AUTHOR]

The newly proposed materials demonstrated outstanding and effective radiation shielding capabilities and promising mechanical properties. A series of (20-x) SrO-(73)B 2 O 3 -(5)TeO 2 -(1)ZnO-(1)Bi 2 O 3 doped with x-Dy 2 O 3 have been produced employing the traditional melt-quench process, with the concentration of Dy 2 O 3 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 Dy 2 O 3 content. The insert of Dy 2 O 3 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 Dy 2 O 3 1 mol%, indicating the influence of Dy 2 O 3 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. Dy 2 O 3 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 Dy 2 O 3. 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. [ABSTRACT FROM AUTHOR]

The current study investigated Saudi Arabian oil fly ash impacts on Egyptian clay bricks' structural and radiation shielding properties. To produce the required bricks, crushed clay minerals from the Hafafit area were mixed with 0, 10, 20, 30, and 40 % wt.% Saudi Arabian oil fly ash and pressed at a pressure rate of 68.55 MPa. Identification of the minerals in the chosen clay was achieved via X-ray diffraction. Additionally, the material's morphology and chemical composition were determined through scanning electron microscope and energy-dispersive X-ray. The fabricated bricks' density was reduced by 36.3 % through increasing the concentration of fly ash from 0 to 40 wt%. Then, the fly ash addition's influence on the fabricated clay bricks' γ-ray shielding properties was investigated by Monte Carlo simulation, which found a reduction in the fabricated bricks' linear attenuation coefficient (LAC) by 41.2, 36.0, 33.8, and 33.8 % at the 0.059, 0.103, 0.662, and 1.252 MeV γ-ray energies, respectively. The LAC reduction caused an increase in the fabricated bricks' half-value thickness, transmission factor, and the equivalent thickness of the lead. Moreover, the thicker fabricated sample thicknesses were found to have high γ-ray shielding capacity and can thus be used in radiation shielding applications.

Composite materials based on a polymer matrix of linear low-density polyethylene (LLDPE) and W were produced by thermal pressing. The content of W in the samples varied from 0 to 70 %. The recycling properties of LLDPE are demonstrated in this study, which significantly helped to reduce the defects. The microstructure of the composites consists of well-defined W grains covered by elastic LLDPE fibers. A homogeneous distribution of tungsten in the polymer matrix was observed for sample W70. The EDX analysis showed the presence of tungsten and carbon (from the polymer component). The XRD analysis confirms the increase in W content in the samples. The FTIR spectra of the composites showed an increase in the content of terminal methyl groups, a decrease in the molecular weight, and a decrease in the degree of crystallinity of the polyethylene matrix with an increase in the W content in the composite. The sample with 70 % W content has the highest effective density (2.61 g/cm3). The sample relative density ranges from 93.3 to 97.7 %. The porosity of LLDPE-W composites does not exceed 7 %. Gamma radiation shielding efficiency parameters such as LAC, HVL, and MFP were calculated using Phy-X/PSD. The radiation source was Co60, with an emission range of 0.8–2.5 MeV. As the gamma energy increases, it is observed that the values of all the parameters deteriorate. However, the sample with a maximum W content of 70 % has the best values of LAC, HVL, and MFP among the other samples.

We report a comprehensive investigation on customization process of Oxide Dispersion-Strengthened alloys through Sm 2 O 3 , Pr 2 O 3 , and Er 2 O 3 incorporation into 316L stainless steel matrix in terms of a desired enhancement in structural, physical, and nuclear radiation shielding properties. Oxide powders are incorporated into 316L stainless steel powder all with the same purity of 99.5%. These were Erbium oxide (Er 2 O 3), Praseodymium oxide (Pr 2 O 3), and Samarium oxide (Sm 2 O 3). First, X-Ray diffraction and Scanning Electron Microscope/Energy-dispersive X-ray spectroscopy analyses are conducted in order to investigate their physical and structural properties. Next, two different experimental setups are employed using a133Ba and 241Am/Be sources for the measurements of gamma-ray and neutron transmission properties of Oxide Dispersion-Strengthened alloys. The maximum density increment is achieved through Er 2 O 3 compared to other reinforced oxides. The detector counting value reached its minimum level when a 5% Er 2 O 3 oxide dispersion was introduced into the 316L SS matrix. Similarly, the most significant degree of photon absorption, the highest values of mass attenuation coefficient, lowest half value layer, and most effective atomic number, were all attained by the same sample. Based on the findings derived from the investigation, it can be concluded that incorporating Er 2 O 3 oxide into 316L steel can be considered as a viable option in terms of enhancing the critical properties of Oxide Dispersion-Strengthened alloys for extreme conditions such as nuclear reactors and other similar fields, where the behavioral attributes of the utilized materials are at utmost importance. [ABSTRACT FROM AUTHOR]

This study presents a new approach towards the production of sol-gel silica-coated Bi2O3/Gd2O3 cement additives towards the improvement of early mechanical performance and radiation attenuation. Two types of silica coatings, which varied in synthesis method and morphology, were used to coat Bi2O3/Gd2O3 structures and evaluated as a cement filler in Portland cement pastes. Isothermal calorimetry studies and early strength evaluations confirmed that both proposed coating types can overcome retarded cement hydration process, attributed to Bi2O3 presence, resulting in improved one day compressive strength by 300% and 251% (depending on coating method) when compared to paste containing pristine Bi2O3 and Gd2O3 particles. Moreover, depending on the type of chosen coating type, various rheological performances of cement pastes can be achieved. Thanks to the proposed combination of materials, both gamma-rays and slow neutron attenuation in cement pastes can be simultaneously improved. The introduction of silica coating resulted in an increment of the gamma-ray and neutron shielding thanks to the increased probability of radiation interaction. Along with the positive early age effects of the synthesized structures, the 28 day mechanical performance of cement pastes was not suppressed, and was found to be comparable to that of the control specimen. As an outcome, silica-coated structures can be successfully used in radiation-shielding cement-based composites, e.g. with demanding early age performances. [ABSTRACT FROM AUTHOR]

The main objective of this study is to develop 3D printed heavyweight concrete (3DPHWC) to produce elements with a dry density of up to 3500 kg/m3 by replacing natural aggregate (SA) with magnetite aggregate (MA) up to 100%. A comprehensive systematic study was conducted to thoroughly assess mixtures' mechanical properties, physical proficiency, fresh properties, and printing qualities. The inclusion of MA exhibited the desired fresh properties required for 3D printing and promising physical and mechanical properties. Evaluation of the mechanical properties of designed 3DPHWC indicates that replacing SA with MA increases both cast and printed samples' strengths. The 3D printed M100 sample achieved higher 28 days flexural and compressive strengths by 18 % and 20 %, respectively, compared to printed control mix (M0). Micro-CT study correspondingly demonstrated improvements in the composites' porosity, pore size, and pore morphologies. The linear attenuation coefficients (LACs) and half-value layer (HVLs) for slow neutron and gamma-ray were measured to assess radiation shielding characteristics. A significant performance improvement was obtained for slow neutrons by introducing the magnetite aggregate. Unlike slow neutrons, no significant difference was observed between cast and printed samples against γ-rays. Moreover, the effect of porosity on the shielding performance was discussed.

The accuracy of the photoatomic cross-section data is of great importance in the field of radiation protection, particularly in the characterization of radiation shielding materials. With the release of the latest and probably the most accurate photoatomic data library, EPDL2017, the need to re-evaluate all the existing and already established mass attenuation coefficients (MACs) of all radiation shielding materials arises. The MACs of several polymers, alloy-based, glasses, and building materials used in a nuclear medicine facility were investigated using the EPDL2017 library embedded in EpiXS software and were compared to MACs available in the literature. The relative differences between MACEpiXS and MACXCOM were negligible, ranging from 0.02% to 0.36% for most materials. However, for material like a glass comprising of elements Te and La evaluated near their corresponding K-edge energies, the relative differences in MACs increased up to 1.46%. On the other hand, a comparison with MACs calculated based on EPDL97 (a predecessor of EPDL2017) revealed as much as a 6.61% difference. Also, it would seem that the changes in MACs were more evident in the materials composed of high atomic number elements evaluated at x-ray energies compared to materials composed of low atomic number elements evaluated at gamma-ray energies.

5CaF2–5BaF2 – 60B2O3–10TeO2 – (20-x)Na2O – xDy2O3: (0.5 ≤ x ≤ 2.5 mol percent) glasses were studied for their physical, mechanical, and gamma radiation resistance. The density of Dy0.5 and Dy2.5 glass samples containing 0.5 and 2.5 mol of Dy2O3 was changed from 2.98 to 3.09 g/cm3, respectively. The estimated values of longitudinal (LB-C) were altered from 171.085 to 165.390 GPa, bulk (KB–C) from 105.100 to 102.680 GPa, Young's (EB-C) from 128.602 to 122.674 GPa, and shear (SB–C) from 49.612 to 47.150 GPa for mechanical characteristics (GPa). The Poisson's ratio (σB-C) was varied between 0.296 and 0.300. The MCNPX code and Py-MLBUF online calculation platform were used to calculate mass attenuation coefficients for all Dyx-glasses. In terms of quantitative values, the acquired results are in good agreement. For all photon energies, the Dy2.5 glass sample exhibits the highest linear (μ) and mass (μm) attenuation coefficients. All analyzed Dyx-glasses exhibit a similar trend in half-value layer (T1/2) and mean free path (MFP), (T1/2, λ)Dy0.5 > (T1/2, λ)Dy1.0 > (T1/2, λ)Dy1.5 > (T1/2, λ)Dy2.0 > (T1/2, λ)Dy2.5. Over the whole gamma-ray energy range, the Dy2.5 sample has the highest effective atomic number (Zeff) values. Across the whole photon energy and penetration depth range, the Dy2.5 has the lowest EBF and EABF values. Because of the maximum contribution of Dysprosium (III)-oxide, the Dy2.5 sample can be deemed superior in terms of gamma-ray shielding qualities.

The linear attenuation coefficient (LAC), mean free path (MFP), half-value layer (HVL), and the radiation protection efficiency (RPE) parameters of Lombok pumice powder from 3 different regions (Ijobalit, Setangi beach, and Lingsar) have been analyzed. The radiation parameter analysis was carried out to determine the pumice that potential as a raw material of radiation shielding composite. The Monte Carlo simulation using the GEANT4 toolkit was applied to analyze those parameters using a gamma-ray transmission measurement for the photon energies of 57Co, 133Ba, 54Mn, 137Cs, 60Co, 65Zn, 22Na and 40K. The GEANT4 simulation results were compared to the XCOM theoretical calculation and show that the linear attenuation coefficient parameter has a good agreement with the XCOM results based on the determination coefficient of the correlation graph (R² = 0.998) between those 2 approaches methods. Setangi beach pumice has a smaller LAC parameter than Ijobalit pumice and Lingsar pumice. The MFP and HVL parameter of the Setangi beach pumice indicate the absorption ability of gamma photons is low. In the low gamma energy 0.122 MeV, Ijobalit pumice and Lingsar pumice have more than 50 % RPE and are better used as a raw material of radiation shielding composite. [ABSTRACT FROM AUTHOR]

• TiNbWMoZrOx integration markedly boosts zinc-tellurite glass radiation shielding. • The highest shielding efficacy was observed at a 4 mol% of tinbwmozro x. • Enhanced gamma-ray absorption and neutron attenuation achieved with HEO-doped glasses. • The novel HEO inclusion method redefines radiation shielding material benchmarks. • The study establishes HEOs as promising for advanced radiation protection applications. While numerous oxide additives have traditionally been employed to enhance the radiation shielding capabilities of glasses, the unique attributes of high-entropy oxides (HEOs), a group of materials acclaimed in contemporary material science for their distinctive properties have remained unexamined in this specific area. This novel study explores the enhancement of radiation shielding properties in zinc-tellurite glasses through the integration of TiNbWMoZrO x High Entropy Oxides (HEO). Utilizing advanced synthesis techniques, including mechanical alloying and oxidation, the research successfully incorporates HEOs into glass matrices, aiming to improve gamma-ray and neutron attenuation. Characterization through X-ray diffraction (XRD), scanning electron microscopy (SEM), and X-ray photoelectron spectroscopy (XPS) confirms the uniform distribution and structural integrity of the HEOs within the glasses. The synthesis of glass samples with a base structure suitable for the molar composition of 25ZnO.75TeO 2 (mol%) and glass samples doped with TiNbWMoZrO x (HEO) was carried out using the traditional high-temperature melting and annealing method. The outcomes demonstrate a concentration-dependent increase in shielding efficacy, particularly highlighting the superior performance of glasses doped with 4 mol% of TiNbWMoZrO x (HEC2–4), which exhibit significantly enhanced mass attenuation coefficients, lower half-value layers, and higher effective atomic numbers. This indicates the effective role of HEOs in boosting radiation protection capabilities. Comparative analysis with traditional shielding materials showcases the HEC2–4 glasses' competitive advantage, underlining their potential as a versatile shielding solution. It can be concluded that incorporating TiNbWMoZrO x high entropy oxides into zinc-tellurite glasses significantly augments their radiation shielding properties, offering a novel approach for enhancing protection against gamma-ray and neutron in various applications. [ABSTRACT FROM AUTHOR]

This study explores the gamma-ray and neutron shielding properties of fourteen different concrete samples, each tailored with varying percentages of Boron Carbide, Iron, and Iron Boride. Using the MCNP 6.3 Monte Carlo code, we calculated transmission factors for photon energies of 0.662 MeV, 1.1732 MeV, and 1.3325 MeV, and analyzed the impact of concrete thickness on shielding efficacy. Additionally, the Phy-X/PSD software was used to compute critical parameters such as linear and mass attenuation coefficients, half-value layer, tenth-value layer, mean free path, and fast neutron removal cross-section to gain a comprehensive understanding of each material's shielding capabilities. Our findings indicate that adding iron to the concrete matrix significantly enhances its attenuation properties, with the 20%Fe+80%Concrete sample outperforming all others. This composition demonstrated the lowest transmission factors across all tested energies and thicknesses, indicating superior photon attenuation. Moreover, the 20%Fe+80% Concrete exhibited the highest fast neutron removal cross-section, making it highly effective for environments requiring neutron shielding. In addition to the shielding properties, we analyzed the Elastic (Young's) Modulus of the concrete samples to understand their mechanical properties. Standard Concrete had an Elastic Modulus of 261.24 GPa, while the introduction of boron carbide significantly enhanced the Elastic Modulus, with pure boron carbide concrete exhibiting a value of 518.88 GPa. Concrete samples with varying percentages of boron carbide (5%, 10%, 15%, and 20%) showed a progressive increase in Elastic Modulus, indicating that higher proportions of boron carbide consistently enhance the material's stiffness. Conversely, concrete samples with iron boride and iron showed slight reductions in Elastic Modulus. It can be concluded that the boron carbide enhances stiffness, iron and iron boride provide a balance between stiffness and other properties. In conclusion, the 20%Fe+80%Concrete is a standout material that could greatly improve radiation shielding, offering major benefits. • 20%Fe+80%Concrete shows highest photon attenuation across tested energies and thicknesses. • Boron carbide addition significantly increases the Elastic Modulus of concrete samples. • 20%Fe+80%Concrete demonstrates the highest fast neutron removal cross-section. • Iron addition improves gamma-ray shielding, enhancing safety and cost-effectiveness. • Elastic Modulus varies with composition, indicating material stiffness adjustments are possible. [ABSTRACT FROM AUTHOR]

• Five tellurium-lead-borate-based glass systems were prepared and modified with ZrO 2. • Substituting B 2 O 3 with ZrO 2 increases the density and the γ-ray shielding ability. • Unlike fast neutron, ZrO 2 addition enhances the slow neutron attenuation. This research investigates the impact of adding Zirconia (ZrO 2) to tellurium-lead-borate glasses, focusing on how it affects their physical, optical, and radiation shielding properties, particularly against gamma-rays and neutrons. Key parameters for gamma-ray shielding (mass attenuation coefficient (µ m), effective atomic numbers (Z eff), and effective electron densities (N eff)) were measured across an energy range of 0.080 to 2.614 MeV. Notably, excellent agreement (within 0.5 %) was observed between the measured and calculated µ m values. For slow neutron attenuation measurements, we employed a 241Am-Be neutron source in conjunction with a BF 3 detector. Fast neutron attenuation was assessed using the NXCOM software to determine the effective macroscopic removal cross-section (Σ R). The addition of Zirconia notably enhanced the glass density (∼6.8 %) and its ability to shield against gamma-rays (∼10 %) and slow neutrons (∼71 %). However, this improvement comes with a slight trade-off: a decrease of approximately 1.5 % in fast neutron attenuation was observed. This trade-off between shielding effectiveness for different radiation types warrants further investigation to optimize glass compositions, considering the desired balance between shielding performance across various radiation spectrums. [ABSTRACT FROM AUTHOR]

Copper-doped lithium calcium fluorophosphate glasses in the compositional system (60− x)P 2 O 5 ·20LiF·20CaF 2 · x CuO (x = 0−3 mol%) were prepared using the conventional melt quenching technique. X-ray diffraction confirmed the amorphous, non-crystalline phase of the glasses. Optical absorption spectra indicated the presence of additional broad visible-NIR absorption bands upon CuO doping, attributed to distorted Cu2+ ions. Possible overlaps from Jahn-Teller distorted sites or clustering into nanodomains may contribute to band broadening. The direct optical bandgap was found to reduce from 3.89 eV to 1.17 eV with increasing CuO content. The study of physical parameters showed almost linear variation in density (2.62–2.95 g/cm3) and molar volume (40.45–35.29 cm3/mol) with incremental CuO substitution, explained by changes in structural packing efficiency and formation of Cu–O complexes. FTIR spectra revealed vibrations corresponding to phosphate structural groups. The simulation of radiation shielding parameters displayed steady improvements with higher CuO fractions, which were related to enhanced photon interactions via photoelectric absorption and Compton scattering. • Copper-doped lithium calcium fluorophosphate glasses were prepared via melt quenching. • X-ray confirms the amorphous nature and IR spectra revealed vibrations corresponding to phosphate groups of the samples. • Increasing CuO contents reduced the direct optical bandgap from 3.89 eV to 1.17 eV. • Density and molar volume varied linearly with CuO substitution due to Cu–O complex formation. • The obtained data enhances the gamma-ray attenuation parameters of the P 2 O 5 –LiF–CaF 2 system. [ABSTRACT FROM AUTHOR]

In this study, we studied the gamma radiation shielding properties of ternary germanate glass systems containing Bi2O3, PbF2, and B2O3. The glass samples were synthesized by using the traditional melt‐quenching method. X‐ray Diffraction (XRD) measurements were performed to confirm the glassy nature of the synthesized materials. A narrow‐beam transmission geometry equipped with a NaI(Tl) scintillation detector was used to measure experimentally measurable shielding parameters of the samples, like mass attenuation coefficient, linear attenuation coefficient, half‐value layer, and effective atomic number. Measurements were performed at gamma‐ray energies of 662, 1173, and 1332 keV emitted from 137Cs and 60Co radioactive sources. Additionally, all the above parameters were also calculated theoretically in the.015–15 MeV energy region by employing the WinXCOM software to verify the experimental findings. The experimental and theoretical results were found to be in good agreement. The results showed that the 70Ge20Bi10Pb glass system has competitive shielding properties among the studied glass systems and could be a good candidate for radiation shielding applications. [ABSTRACT FROM AUTHOR]

In this study, we studied the gamma radiation shielding properties of ternary germanate glass systems containing Bi2O3, PbF2, and B2O3. The glass samples were synthesized by using the traditional melt‐quenching method. X‐ray Diffraction (XRD) measurements were performed to confirm the glassy nature of the synthesized materials. A narrow‐beam transmission geometry equipped with a NaI(Tl) scintillation detector was used to measure experimentally measurable shielding parameters of the samples, like mass attenuation coefficient, linear attenuation coefficient, half‐value layer, and effective atomic number. Measurements were performed at gamma‐ray energies of 662, 1173, and 1332 keV emitted from 137Cs and 60Co radioactive sources. Additionally, all the above parameters were also calculated theoretically in the.015–15 MeV energy region by employing the WinXCOM software to verify the experimental findings. The experimental and theoretical results were found to be in good agreement. The results showed that the 70Ge20Bi10Pb glass system has competitive shielding properties among the studied glass systems and could be a good candidate for radiation shielding applications. [ABSTRACT FROM AUTHOR]

The melt-quenching technique was used to prepare five samples of antimony (III) oxide (Sb2O3) glasses with chemical composition of ySb2O3-15CaO-15Li2O-(70 − x)B2O3: y = 0 (Sb0), 1 (Sb1), 3 (Sb3), 5 (Sb5), and 8 (Sb8) mol.%. The physical and optical characteristics and the gamma-radiation protection effectiveness within 0.015–15 MeV photon energy were investigated. XRD patterns for all Sb glasses confirmed their amorphous nature. The density of the Sb glasses was gradually increased from 2.410 g/cm3 to 2.780 g/cm3. Both the optical energy band gap (Eg) and Fermi energy level (EF) were increased as a function of increasing antimony (III) oxide content in the glass network: Eg = 2.56 eV, 2.58 eV, 2.62 eV, 2.90 eV, and 2.97 eV, and EF = 3.68 eV, 3.45 eV, 3.69 eV, 3.97 eV, and 3.99 eV for Sb0, Sb1, Sb3, Sb5, and Sb8 glasses, respectively. Insertion of the Sb2O3 in the glass matrix enhanced the mass attenuation coefficient (MAC) of the Sb glasses. The highest MAC values were achieved for Sb8 glass, while the lowest MAC values were achieved for Sb0 glass for all photon energy. Generally, the MAC followed the order (Sb8)MAC > (Sb5)MAC > (Sb3)MAC > (Sb1)MAC > (Sb0)MAC. In terms of the half-value layer (HVL) parameter, Sb0 glass demonstrated the highest HVL values, while Sb8 glass demonstrated the lowest values. The effective atomic (Zeff) and electron (Neff) numbers showed the same trend as (Sb8)Zeff, Neff > (Sb5)Zeff, Neff > (Sb3)Zeff, Neff > (Sb1)Zeff, Neff > (Sb0)Zeff, Neff. Both the total atomic (ACS) and the total electronic (ECS) cross-sections were enhanced with increasing antimony (III) oxide content in the glass network. In comparison, our findings confirm that the Sb8 sample is superior for radiation protection among all prepared Sb glasses. On the other hand, the Sb glass is better than some commercial radiation shielding materials such as concrete and RS-253-G18 glasses. [ABSTRACT FROM AUTHOR]

In this study, we synthesized binary germanate glasses with compositions of GeO2 – Bi2O3, GeO2 – PbF2, and GeO2 – V2O5. The traditional melt-quenching method was used for glass synthesis. The radiation shielding properties of the synthesized samples were calculated theoretically and measured experimentally as well. A narrow-beam transmission geometry, which uses a NaI(Tl) detector, was employed to measure linear attenuation coefficient, mass attenuation coefficient, half-value layer, and effective atomic number values of the glasses at gamma-ray energies of 662, 1173, and 1332 keV and, 137Cs, and 60Co radioactive point sources were used to produce gamma-ray photons of these energies. Additionally, all the above parameters were also calculated theoretically using the WinXCOM software in the 0.015-15 MeV energy range to confirm the accuracy of the measurements. A good agreement between theoretical and experimental findings was observed. It was also found that the increase in the concentrations of Bi2O3, PbF2, and V2O5 network modifiers improved the radiation shielding capacity of synthesized germanate glasses. The results revealed that the GeBi30 glass has superior shielding properties among the synthesized germanate glasses. [ABSTRACT FROM AUTHOR]

• Radiation shielding abilities of concrete which is good in environmental protection. • Recycling and reusing of waste glass in a useful way addresses waste management. • The use of waste glass as additive, which solved the material selection problem. • Solution to problem of finding optimal composition to for best shielding in concrete. • Solution to problem of identifying most efficient shielding material composition. • Use of local materials align with aim of SDG, addressing environmental sustainability. 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. [ABSTRACT FROM AUTHOR]

[Display omitted] • The Gadolinium doped phosphate glass was produced using conventional melt quenching technique. • The Gadolinium doped Phosphate glass emits summer sunlight (blue sky) and its color coordinates are very close to white light. • The mass attenuation coefficient of the prepared glass was found to be 4592 cm2/g at 0.001 MeV. • The mean free path value of gadolinium doped phosphate glass was measured to be 11.85 cm at 15 MeV. • The produced glass's high Z eff value confirms its ability to function as a shielding material, according to the Phy-X study. Gadolinium doped phosphate glass was created with a composition of 70 P 2 O 5 + 5Al 2 O 3 + 5 Ba 2 CO 3 + 9 KF 2 + 5 MnO 2 + 5 SnO+1 Gd 2 O 3 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. [ABSTRACT FROM AUTHOR]

In this study, the radiation shielding effectiveness of iron phosphate glass (Fe 2 O 3 –P 2 O 5) doped with antimony (Sb) and tellurium (Te) is assessed in detail using advanced computational methods. The projected range, mass stopping power, and KERMA (Kinetic Energy Released per unit MAss) for fourteen different iron phosphate glass samples are calculated through the PAGEX and SRIM software. Mass attenuation coefficients, linear attenuation coefficients, mean free path, half value layers, tenth value layers, and effective atomic number are determined in 0.015–15 MeV energy range. The research reveals that doping iron phosphate glass with Sb 2 O 3 significantly enhances its shielding capabilities when compared to the inclusion of TeO 2. Another important aspect is, the IPGSb50 sample exhibited the highest KERMA values, indicating its exceptional capacity for energy absorption from ionizing radiation. Additionally, the IPGSb50 sample exhibited the lowest projected range for alpha particles, also this sample demonstrated a similar prowess in limiting the penetration of proton particles. Our findings indicate that the incorporation of Sb 2 O 3 and TeO 2 into iron phosphate glass matrices results in a noticeable improvement in gamma radiation shielding effectiveness. These doped glasses could serve as potent alternatives to traditional lead-based shielding materials, offering a safer and potentially more effective barrier against a variety of radiation types. • Investigated radiation shielding in iron phosphate glass doped with antimony and tellurium using advanced computations. • Analysed fourteen samples for mass stopping power, KERMA values, and gamma attenuation parameters. • Found antimony-doped glass significantly outperforms tellurium-doped glass in radiation shielding effectiveness. • Research implications include applications in medical imaging, nuclear energy, and space exploration sectors. [ABSTRACT FROM AUTHOR]

In this study, three different sliding bearing alloy samples were investigated in terms of their performance on attenuation characteristics and behavioral attitudes under 0.015–15 MeV gamma-ray exposure. Accordingly, different types of advanced calculation methods were utilized to calculate the radiation shielding parameters. Next, several gamma-ray shielding parameters and exposure rates in addition to fast neutron removal cross-section were determined. Furthermore, exposure and energy absorption buildup factors were determined by using G-P fitting method. Mass attenuation coefficients (MAC) values were recorded as 2.5246, 2.5703, and 2.5827 (cm2/g) for Alloy1, Alloy2, and Alloy3 samples at 15 MeV photon energy, respectively. At 40 mfp, the highest EBF values were reported as 1,376,274, 1,003,593, and 969,373 for Alloy1, Alloy2, and Alloy3 samples. The results of this extended investigation showed that the Alloy3 sample with the highest Pb reinforcement amount has superior shielding capability among the investigated samples. It can be concluded from the results that substitution of Pb with Bi in the recent alloy structure has a monotonic effect on different types of shielding parameters. Therefore, it can also be concluded that Pb is a remarkable tool for the improvement of the shielding properties of studied alloy structures. [ABSTRACT FROM AUTHOR]

Sodium borosilicate glasses of the composition 47SiO2–13B2O3–20Na2O–(20–x)CaO–xMgO: x = 0, 5, 10, 15, and 20 mol% named as Mg0, Mg5, Mg10, Mg15, and Mg20, respectively, have been synthesized via melt quenching method. The effect of combined ionic substitutions on composition, physical, linear optical, and photon shielding properties was investigated. The density was decreased from 2.6236 to 2.5155 g cm−3, while the molar volume was decreased from 23.2133 to 22.957 cm3 mol−1 for Mg0 to Mg20. The oxygen packing density and field strength were enhanced with increasing Mg2+ ion content. Therefore, the glass structure's rigidity was supported by the decrease in internuclear distance and polaron radius values with increased dopant ion concentration. The optical energy gap was increased from 3.24 to 3.35 eV, and the refractive index from 2.335 to 2.309 for Mg0 to Mg15 glasses. The linear attenuation coefficient of the proposed Mg0-Mg20 glasses obeys the trend (Mg20)LAC < (Mg15)LAC < (Mg10)LAC < (Mg5)LAC < (Mg0)LAC, while the mean free path obeys the trend (Mg0)MFP < (Mg5)MFP < (Mg10)MFP < (Mg15)MFP < (Mg20)MFP. The half value layer (HVL) of Mg0 ranged from 0.034 to 12.546 cm, while Mg20 ranged from 0.061 to 13.714 cm at 0.015 and 15 MeV. The transmission factor was found 43.713% and 75.864% at 5-cm glass thickness and increased to reach 85.35267% and 95.07127% at 1-cm glass thickness at 1 MeV and 15 MeV, respectively. The suggested glasses can be applied in optical devices and radiation protection applications. [ABSTRACT FROM AUTHOR]

This work aims to compare the performance between natural rubber (NR) composites with lead oxide (PbO) and bismuth oxide (Bi2O3) as shielding fillers for gamma radiation shielding applications. Modulus at 100% elongation, tensile strength, elongation at break, hardness and a specific gravity of the NR composites were investigated. The results indicated that NR/Bi2O3 and NR/PbO composites have no significant difference in terms of modulus and hardness values, while the NR/PbO composite exhibited better tensile strength and specific gravity than that of NR/Bi2O3 composite. However, NR/Bi2O3 composite exhibited better performance in oil resistance and thermal stability than the one with PbO. Gamma radiation shielding properties including mass attenuation coefficient ( μ m ), effective atomic number (Zeff), effective electron density (Ne) and half-value layer (HVL) have also been studied. It is seen that both the composites exhibited better radiation shielding properties. Furthermore, the radiation properties were in good agreement with the calculated theoretical values. In addition, both the composites of NR with PbO and Bi2O3 particles showed excellent radiation shielding properties compared to neat NR as well as commercially available materials including window, ordinary concrete and haematite-serpentine. The material developed in the present investigation can be used as efficient flexible radiation shielding materials. However, lead (Pb) is not suitable to use as a radiation shielding material due to its toxic nature to the human and the environment. Therefore, NR with Bi2O3 is an appropriate choice for producing novel wearable radiation shielding materials to manufacture gloves, aprons, rubber underwear and other wearable materials. [ABSTRACT FROM AUTHOR]

Characteristics of tellurite-tungstate-antimonate glasses containing heavy metal oxide were investigated in detail using two methods: the MCNPX Monte Carlo code and the Phy-X/PSD platform. The influence of Sm2O3, translocating with TeO2 at ratios of 0.2, 0.5, 0.8, 1, and 1.5 mol% on radiation shielding properties of glasses, was set forth with five glass structures determined according to the (75-x)TeO2-15Sb2O3-10WO3-xSm2O3 glass composition. Densities of the glasses were prepared by doping a low ratio of Sm2O3 that varied between 5.834 and 5.898 g/cm3. Sample densities, which have an important role in determining radiation shielding character, increased depending on the increase in Sm2O3 concentration. Effective removal cross-section (∑R) values against fast neutrons, as well as linear and mass attenuation coefficients, half-value layer, mean free path, variation of effective atomic number against photon energy, exposure, and energy built-up factors, were simulated with the help of these two methods. As a result of these estimates, it can be concluded that values obtained using both methods are consistent with each other. From the obtained values, it can be concluded that the SM1.5 sample containing 1.5 mol% would have the most efficient role in radiation shielding. An increase of Sm2O3 resulted in a significant increase in linear and mass attenuation coefficients and effective removal cross-section values belonging to fast neutrons and, in addition, resulted in a decrease in the half value layer. Doping HMO glasses with Sm2O3 was observed to contribute directly to the development of radiation shielding properties of the glass. [ABSTRACT FROM AUTHOR]

The impact of chromium oxide (Cr2O3) on the organizational, physical, mechanical, and photon shielding qualities of new chromium borate glasses with the chemical composition 50B2O3-25Bi2O3-25Li2O3-xCr2O3 (x=0 (Cr-00), 0.2 (Cr-0.2), 0.4 (Cr-0.4), 0.8 (Cr-0.8), and 1.5 (Cr-1.5) wt%) is investigated. The amorphous behavior of these glasses was verified via X-ray diffraction (XRD) and scan electron microscope (SEM) micrographs. Fourier transform infrared (FTIR) spectra of prepared glass samples revealed the presence of absorption bands due to Cr3+ ions. The density (ρglass) increased as the Cr2O3 concentration increased. The mass attenuation coefficients (MACs) of the proposed glasses were evaluated via the FLUKA code, XCOM program, and Phy-X/PSD software. The MACs values followed this trend: (MAC)Cr-00 < (MAC)Cr-0.2 < (MAC)Cr-0.4 < (MAC)Cr-0.8 < (MAC)Cr-1.5. At 0.015 MeV, the calculated linear attenuation coefficient (LAC) values were 127.913, 133.559, 137.984, 147.034, and 156.212 cm-1 for the Cr-00, Cr-0.2, Cr-0.4, Cr-0.8, and Cr-1.5 glass samples, respectively. The half-value layer (HVL) and mean free path (MFP) values followed this trend: (MAC,MFP)Cr-00 > (MAC,MFP)Cr-0.2 > (MAC,MFP)Cr-0.4 > (MAC,MFP)Cr-0.8 > (MAC,MFP)Cr-1.5. The Cr-00 glass sample had the lowest effective atomic number (Zeff) values, while the Cr-1.5 glass sample had the highest. The calculated exposure buildup factor (EBF) values decreased as the Cr2O3 content increased. The Cr-1.5 sample had a higher effective removal cross-section for fast neutrons (ΣR) value than other radiation shielding materials. The addition of Cr2O3 increased the rigidity and elastic constants (Young's (Y), bulk (K), shear (G), and longitudinal (L) moduli) and improved the level of radiation shielding provided. The prepared glasses can be used as gamma and neutron shielding tools in the medical area. [ABSTRACT FROM AUTHOR]

The ionizing radiation has been well known for over 100 years now, and it was proved that it is harmful to living organisms. On the other hand, physical properties of this radiation itself, and nuclear fission that is the main source of it, find numerous applications. In these circumstances it is crucial to protect humans from exposure to this radiation and develop shielding materials. There are many well-known materials that could be employed for this purpose, unfortunately these materials exhibit many features that make their use difficult (high density, toxicity, etc.). Therefore, intensification of research on the widely understood nanotechnology has brought a huge step in the field of nanomaterials, and this kind of materials could be applied to manufacture shielding materials free from disadvantages of metals. In the era of ecological crisis, focused on the use of nuclear energy, it is even more desirable. This review paper is an attempt to summarize and systematize knowledge in the field of employing nanomaterials in X and gamma shielding. Based on the available experimental data, the linear and mass attenuation coefficients were summarized depending on the used source. Finally, the perspectives and ideas for further work in this field have been presented. • It has been concluded, that the nanocomposites are constantly achieving more attention as potential candidates in the radiological protection. • It has been shown, that various nano- and microparticles, as well as various matrices are used in the nanocomposites composition. • The experimentally-determined linear and mass attenuation coefficients were summarized in the tables. • The content of nano- and microparticles in the base ingredients is wide, which was summarized graphically. [ABSTRACT FROM AUTHOR]

Research into the eco-friendly utilization of red mud or bauxite residue (BR) is expanding globally. This study successfully incorporated BR into a family of glasses through the melt quenching technique. The family have a composition of xBR. (50-x) B 2 O 3.25CaO.25BaO, where x = 0, 5, 10, and 15 wt%. X-ray diffraction (XRD) analysis confirmed the non-crystalline nature of the glasses. Physical properties were studied by measuring density, and microhardness was estimated using Vickers hardness (HV) tests. Differential scanning calorimetry (DSC) was used to evaluate the thermal behavior. Changes in various properties resulting from the presence of BR confirmed modifications in the glass network. The radiation shielding properties were measured for gamma and slow neutrons and calculated for fast neutrons. The results indicated that incorporating BR significantly enhanced the γ-ray shielding capacity, reduced the effectiveness of slow neutron shielding, and had minimal impact on shielding against fast neutrons. Additionally, the glasses were compared to standard radiation concrete mixes, demonstrating their superiority and high potential for use in shielding against gamma/X-ray. • Red mud has been successfully incorporated into a family of glasses. • The family has a composition of xBR. (50-x) B 2 O 3.25CaO.25BaO, where x = 0, 5, 10, and 15 wt%. • The physical and radiation properties were investigated. • Neutron and gamma ray shielding capacity were determined. [ABSTRACT FROM AUTHOR]

The gamma-ray and fast/thermal neutron shielding properties of bismo-borate glasses modified with Nd 2 O 3 in the form B 2 O 3 –Bi 2 O 3 –SrO-Nd 2 O 3 (BBSN0.0-BBSN5.7) were investigated. The newly developed Phy-X/PSD software and Geant4 simulation code were performed to achieve this goal by evaluating several parameters such as MAC, gamma photons dose rate, FNRCS, and scattering/absorption lengths and cross sections for thermal neutrons. At low photon energy; 0.015 MeV, MAC values varied from 76.72, 76.57, 76.43, 76.29, 76.10, and 75.93 cm2 g−1 for BBSN0.0, BBSN1.0, BBSN2.0, BBSN3.0, BBSN4.3, and BBSN5.7, respectively. The HVL followed reversible trend as follows; BBSN0.0 > BBSN1.0 > BBSN2.0 > BBSN3.0 > BBSN4.3 > BBSN5.7. The highest values for Z eff were found at low energy photon range (0.015 MeV) with the values of 76.71, 76.35, 76.00, 75.65, 75.21, and 74.75, while the lowest values were found at 1.5 MeV; 21.32, 21.42, 21.52, 21.61, 21.73, and 21.87 for BBSN0.0 – BBSN5.7, respectively. The gamma dose rate has a dramatic decrease with increasing the glass thickness from 1 mm to 5 mm. Furthermore, glasses with the highest concentration of Nd 2 O 3 show the best thermal/fast neutron shielding capability among the investigated glasses. One can conclude that BBSN5.7 glass owns the best shielding capacity among all BBSN glasses due to the highest LAC values comparing to other selected ones. [ABSTRACT FROM AUTHOR]

Six glass samples with the composition of TeO 2 -Li 2 O-ZnO were analyzed for their radiation shielding properties. The radiation shielding factors for the lithium-zinc-tellurite glasses were reported using the Geant4 code and Phy-X/PSD program. The transmission factor (TF) was determined for different thicknesses and the results revealed that the TF decreases with increasing the thickness of the glass. For TeLiZ1, increasing the thickness of the sample from 0.4 cm to 1.6 cm led to decrease the transmission of the photon from 0.84 to 0.48 at 0.5 MeV and from 0.94 to 0.76 at 4 MeV. The radiation protection efficiency (RPE) results showed that a thicker glass sample absorbs a higher number of photons, implying that lower radiation pass among the glass, increasing RPE. Also, the glass coded as TeLiZ6 has higher RPE than that of TeLiZ1 glass which suggests that at higher content of TeO 2 (85 mol%), the more efficient the glass is at shielding the incoming photons. The linear attenuation coefficient (LAC) obtained by both methods (Geant4 and Phy-X/PSD showed a good agreement for all the glasses and at all investigated energies. The LAC indicates a strong energy dependence, especially at low energies. The LAC also increases as more TeO 2 is added to the glasses. TeLiZ6 (85TeO 2 -15Li 2 O, ρ = 5.164 g/cm 3) has the highest RPE and lowest TF, while TeLiZ1 (60TeO 2 -15Li 2 O-25ZnO, ρ = 4.976 g/cm3) has the lowest RPE and highest TF. The tenth value layer (TVL) was also determined and it was observed that TVL increases with increasing energy, reaching a maximum value at 10 MeV and varying between 12.919 and 13.808 cm. By contrast, the minimum TVL is reported at 15 keV and varies between 0.0106 and 0.0112 cm. The addition of TeO 2 decreases the TVL, with TeLiZ6 having the least TVL. [ABSTRACT FROM AUTHOR]

The purpose of this work is to investigate the effect of increasing Bi 2 O 3 mol% on the radiation shielding parameters of tellurite glass system with the formula Bi 2 O 3 –Na 2 O– V 2 O 5 – TiO 2 –TeO 2 by using Phy-X/PSD computer software between 15 keV and 10 MeV. The results showed that the attenuation factor is very large at 15 keV. The mass attenuation coefficient (μ/ρ) at 15 keV lies within the range of 55.96–67.03 cm2/g for the selected samples. The μ/ρ for the investigated samples at 10 MeV is in the range of 0.0365–0.0392 cm2/g. The results also revealed that the addition of Bi 2 O 3 enhances the effective atomic number (Z eff) and the sample corresponding to the lowest and highest amount of Bi 2 O 3 (coded as TeBTi1 and TeBTi6) has the lowest and highest Z eff. Moreover, Z eff has high values between 15 keV and 0.1 MeV and the maximum Z eff occurs at 0.1 MeV (equal to 61.01, 62.67, 64.10, 65.34, 66.44 and 67.41 for TeBTi1– TeBTi6 samples respectively). The half value layer (HVL) increased when the energy changes from 15 keV to 10 MeV and the lowest HVL occurs at 15 keV for the sample coded as TeBTi6 and equal to 0.0025 cm, while the HVL at this energy for TeBTi1 is 0.0056 cm. Also, we calculated the tenth value layer (TVL) for the present system and we found that TVL reduces with the increment of Bi 2 O 3 content, and the sample corresponding to 22 and 0 mol% of Bi 2 O 3 and TiO 2 respectively namely TeBTi6 possesses the lowest value of TVL, thus has the best radiation attenuation performance in comparison to other selected glasses. Also, we evaluated the effective removal cross-sections of fast neutrons (∑ R) for the investigated glass system and we found that the ∑ R values increase with increase the concentration of Bi 2 O 3. [ABSTRACT FROM AUTHOR]

The goal of this research is to investigate the influence of three heavy metal oxides (Bi 2 O 3 , BaO and TiO 2) on the gamma rays shielding effectiveness of borosilicate glasses. The Geant4 simulation code has been applied to estimate the mass attenuation coefficients (μ/ρ) of 30B 2 O 3 –(70-x)SiO 2 –xHMO glass systems (where HMO are Bi 2 O 3 , BaO and TiO 2 with 0, 1, 2, 3, 4 and 5 mol%). We estimated the μ/ρ values at six energies (i.e. 0.347, 0.511, 0.826, 1.173, 1.275 and 2.506 MeV). To determine the accuracy of the obtained results, we compared the Geant4 data with those calculated using WinXcom software. The obtained Geant4 values of the selected borosilicate glasses with different concentrations of Bi 2 O 3 , BaO and TiO 2 agreed quite well with the WinXcom results at all energies. The addition of Bi 2 O 3 and BaO increases the μ/ρ values, while the samples doped with TiO 2 showed insignificant changes in μ/ρ values with the addition of TiO 2. All the presented samples have lower HVL than the undoped glass sample (70SiO 2 -30B 2 O 3 sample). This means that the addition of the three dopants (Bi 2 O 3 , BaO and TiO 2) have led to a decrease in the HVL which enhances the attenuation performance of the current samples. [ABSTRACT FROM AUTHOR]

• Nineteen heavy-weight concrete mixes evaluated for radiation shielding performance. • Density of concrete affected shielding performance regardless of aggregate types. • The developed equation can be used to calculate required thickness for shielding. In the present work, an experimental investigation was carried out to evaluate the radiation shielding performance of heavy-weight concrete mixtures prepared using different high-density coarse aggregates that included steel slag, steel shot, and iron ore. Normal-weight limestone aggregate was also used in control mixture as well as for partial replacement of the high-density aggregates in some of the heavy-weight concrete mixtures. Considering different combinations of the normal and high-density coarse aggregates and keeping cement content and water/cement ratio constant, a total of nineteen heavy-weight concrete mixtures were prepared and tested for their dry-density, compressive strength, and nuclear radiation response through gamma-ray intensity measurement. Except the control mixture containing normal-weight limestone aggregate, all eighteen heavy-weight concrete mixtures achieved 28-day dry unit weight in the acceptable range of 2600–3563 kg/m3. The compressive strength of the mixtures varied in the range of 26–45 MPa, all satisfying the requirements of a structural concrete. Radiation shielding performance was influenced by the unit weight of the concrete mixtures regardless of the type of coarse aggregates and the strength class of the concrete mixture. Based on the experimental data, correlations between indicator of the radiation shielding performance and unit-weight of concrete was obtained with a high degree of fit. [ABSTRACT FROM AUTHOR]

Two newly synthesized glass series, 10Bi 2 O 3 -20BaO-(70-x)B 2 O 3 -xTeO 2 , and 10MoO 3 -20SrO-(70-x)B 2 O 3 -xTeO 2 , where x = 0, 35, and 70 mol%, were fabricated using the melt-quenching technique. The fabricated glass samples' physical properties and radiation shielding capabilities were examined. The insertion of TeO 2 into the glass composition increased the density values, with the glass samples labeled BBB-T70 (6.53 g/cm3) and SBM-T70 (5.66 g/cm3) exhibiting the highest density due to the increased concentration of TeO 2. The addition of TeO 2 led to loosely bonded glasses, indicating lower glass stability. Using SRIM and Phy-X/PSD software, the radiation shielding capabilities of the produced samples were investigated for various radiation types, including alpha particles, protons, neutrons, and gamma rays. The increase in TeO 2 content and the reduction in B 2 O 3 revealed significant increases in the linear attenuation coefficient (LAC) values and improved gamma shielding properties. For example, the LAC values at 0.283 MeV are 0.283, 0.367, 0.667, 0.902, 1.095, 1.313, and 1.55315 cm−1 for SBM-T00, SBM-T35, SBM-T70, BBB-T00, BBB-T53, and BBB-T70, respectively. However, the SBM-T00 sample exhibited lower charged particle shielding properties. The SBT-T35 and BBB-T00 samples showed the highest ability to stop fast neutrons. In conclusion, the glass samples synthesized in this work are highly recommended for shielding against various ionizing radiation sources. • The various radiation shielding properties for borate, tellurite, and boro tellurite glass systems were explored. • Comprehensive radiation shielding properties such as photon, neutron, and charged particles were studied. • The comparison study was conducted between two glass systems containing different modifiers and glass formers. [ABSTRACT FROM AUTHOR]

In this study, brass (Cu/Zn) reinforced polymer composites with different proportions of brass powders were fabricated. Different types of nuclear shielding parameters such as mass and linear attenuation coefficients, radiation protection efficiency, half and tenth value layers, and effective atomic number values were determined experimentally and theoretically in the energy range of 0.060–1.408 MeV in terms of gamma-ray shielding capabilities of fabricated polymer composites. A high Purity Germanium detector (HPGe) in conjunction with a Multi-Channel Analyzer (MCA) and twenty-two characteristic gamma-ray energies have been used in the experimental phase. In addition, the exposure and energy absorption buildup factors of reinforced Cu/Zn composites were calculated, and relative dose distribution values were computed to verify them. Proton mass stopping power (ΨP), proton projected range (ΦP), alpha mass stopping power (ΨA), and alpha projected range (ΦA) parameters, which indicate the interactions of the produced composites with charged particle radiation, were investigated. Fast neutron removal cross-section (ΣR) results were determined to give an idea in terms of neutron shielding. According to the obtained results, it is reported that the CuZn20 coded sample’s ability to attenuate gamma-ray and charged particle radiation is more efficient than that of other prepared composites. A CuZn05 coded sample was found to be more suitable for neutron shielding capability.

The build-up factor is a magnitude which allows to correct the photon exponential attenuation model to obtain the real value of a certain dosimetric magnitude, like the absorbed dose in tissue, after the source has crossed a material. Its main weaknesses are the dependences on the response function of such a magnitude, the geometry, and the source directionality. A formalism to deal with the first is presented in this work, which leads to the definition of the differential build-up factor. Analog Monte Carlo calculations were used to calculate this factor, as well as describing its uncertainty, in the 30 keV to 10 MeV energy range for the most typical materials up to 10 mean-free-paths. Coherent scattering and binding effects were considered in the simulations, which make the results suitable for calculations with the most complete descriptions of the attenuation coefficients. Differences due to geometry, source directionality, and detector response variability were typically found to be up to 30% in the studied range. [ABSTRACT FROM AUTHOR]

The activities carried out to obtain public consent for deuterium experiments in LHD, which began in 2017, are reviewed in this paper. In addition, the upgrades and the safety management of LHD for deuterium experiments, including neutron yield measurement system, exhaust detritiation system, institutional regulation for radiation control, and other issues, are briefly presented. During the first campaign of the deuterium experiments in LHD, the shielding of gamma-ray and neutron by the concrete wall of the LHD torus hall was evaluated. Also, the confinement of radioactive isotopes in air inside the torus hall was investigated. No increase of radiation dose was measured outside the torus hall, although the high radiation dose field inside the torus hall was found during deuterium experiments. Therefore, almost all gamma-rays and neutrons were shielded by the concrete wall of the torus hall due to its sufficient thickness of 2 m. The radioactive isotopes in air as well as in other components were well confined in the torus hall. In particular, the pressure control inside the torus hall being lower than outside the torus hall effectively prevented the radioactive isotopes in air from diffusing to the unprescribed area. [ABSTRACT FROM AUTHOR]

[Display omitted] • Printable heavyweight mixes with maximum dry density of 3500 kg/m3 were developed. • Mix containing 60% of magnetite aggregate exhibited the highest green strength. • Mixes containing MA displayed an adequate fresh property performances for medium scale printing. • The incorporation of MA gradually increases the flexural and compressive strengths of both cast and printed samples. • A substantial improvement in gamma-ray and neutron shielding was reported in mixes incorporating MA. The main objective of this study is to develop 3D printed heavyweight concrete (3DPHWC) to produce elements with a dry density of up to 3500 kg/m3 by replacing natural aggregate (SA) with magnetite aggregate (MA) up to 100%. A comprehensive systematic study was conducted to thoroughly assess mixtures' mechanical properties, physical proficiency, fresh properties, and printing qualities. The inclusion of MA exhibited the desired fresh properties required for 3D printing and promising physical and mechanical properties. Evaluation of the mechanical properties of designed 3DPHWC indicates that replacing SA with MA increases both cast and printed samples' strengths. The 3D printed M100 sample achieved higher 28 days flexural and compressive strengths by 18 % and 20 %, respectively, compared to printed control mix (M0). Micro-CT study correspondingly demonstrated improvements in the composites' porosity, pore size, and pore morphologies. The linear attenuation coefficients (LACs) and half-value layer (HVLs) for slow neutron and gamma-ray were measured to assess radiation shielding characteristics. A significant performance improvement was obtained for slow neutrons by introducing the magnetite aggregate. Unlike slow neutrons, no significant difference was observed between cast and printed samples against γ-rays. Moreover, the effect of porosity on the shielding performance was discussed. [ABSTRACT FROM AUTHOR]

• Steel slag aggregate can be used for concrete admixture of radiation shielding. • Characterization of steel slag from different countries are reported. • The mix design scenario with different percentage of steel slag is summarized. • Concrete containing steel slag has higher mechanical and shielding properties. • Effect of steel slag on gamma and neutron shielding performance is highlighted. Steel slag is a steel industry byproduct that increases in volume as global steel production expands. The steel slag application as natural aggregate replacement in the production of shielding concrete continues to spread. Besides minimizing the negative impact on the environment, the use of steel slag mixtures proved to enhance the performance of concrete as an ionizing radiation shielding. Despite having many advantages, applying steel slag in concrete shielding has several drawbacks. Therefore, this review was carried out to see and map the research effort on steel slag utilization in shielding concrete through the systematic review method and bibliometric analysis. The SCOPUS and Science Direct database screening resulted in the exclusion of 26 studies. This review discusses the characterization of various forms and origins of steel slag, the mix design and mechanical properties of concrete shielding steel slag, and microstructural analysis. The test findings for gamma radiation 60Co, 137Cs, 241Am, and neutron source of 252Cf and Ambe were also discussed in depth. An extensive literature review concluded that adding steel slag to concrete for shielding gamma and neutron radiation can increase compressive and tensile strength but reduce workability. Compared to conventional concrete, steel slag concrete's linear attenuation and removal cross-section is higher, while the half-value layer (HVL) is minimized. However, steel slag composition can expand the volume, diminishing radiation shielding performance at high temperatures. This systematic review gives a comprehensive overview of research gaps and possibilities and will likely encourage researchers to participate in these investigations. [ABSTRACT FROM AUTHOR]

In the present paper, the basic radiation parameters of tellurite glasses with different forming oxides (B2O3, BaO, K2O, V2O5, WO3, and ZnO) have been studied over a wide photon energy range from 1 keV to 100 GeV, using WinXCom program. These parameters are the mass attenuation coefficient ( μ/ ρ), effective atomic number ( Zeff), and electron density ( Ne,eff). In addition, the macroscopic effective removal cross sections (ΣR) for fast neutrons have been calculated. The dependence of different parameters on incident photon energy and chemical content has been discussed. Among the selected glass systems TeO2-WO3 and TeO2-B2O3 showed superior shielding properties for gamma-ray and neutrons, respectively. It is shown that the selected glass systems have higher values of the mass attenuation coefficients ( μ/ ρ) than concretes and 0.7SiO2:0.3BaO glass. These results indicate that tellurite glasses can be used as radiation shielding materials. [ABSTRACT FROM AUTHOR]

In the current study, we fabricated a series of boro-tellurite glass samples with a composition 10SrO–10Al 2 O 3 –10MoO 3 -(70-x)B 2 O 3 -xTeO 2 , where (x = 0, 17.5, 35, 52.5, and 70 mol%) via an ordinary melt-quench method. The glass structure was explored by X-ray diffraction (XRD), physical and structural properties. XRD results affirm the existence of two broad peaks, proving the amorphous state of the current glasses. The acquired results exhibit a linear relationship between the density, Poisson's ratio, and the addition of TeO 2 amounts. The addition of TeO 2 to the glass system shows a rise in glass stability and a reduction in packing density. Additionally, the values of mass attenuation coefficient (MAC) were determined experimentally within five energies (0.184, 0.280, 0.661, 0.710, and 0.810 MeV) from two radiation sources (166Ho and 137Cs). The (MAC) exp results were compared with XCOM values, and the compared values showed excellent compatibility. From the experimental results, many radiation shielding features involving half-value layer (HVL), mean free path (MFP), tenth value layer (TVL), and radiation protection efficiency (RPE) were computed. From the obtained results, it can be concluded that the TeSB4 sample has the highest stability and absorption for radiation, indicating the ability to use it as a radiation shielding substance. • A new series of glass samples were prepared by ordinary melt-quench method. • The prepared samples appeared attractive results in the radiation shielding field. • The shielding properties of all prepared samples were measured experimentally. [ABSTRACT FROM AUTHOR]

[Display omitted] • After 10 h of heat curing, a compressive strength of approximately 160 MPa was obtained. • The filler property of the quartz aggregate decreased the capillarity coefficient of the geopolymers. • Among the geopolymer samples whose photon and fast neutron shielding properties were investigated, the M3 sample has good gamma ray shielding performance due to its high GBFS content. • In addition, the close Ʃ R value with conventional attenuators shows that the M1 sample can be evaluated in nuclear reactor facilities. Today, binders with low CO 2 emissions are preferred in building design. Geopolymers have lower CO 2 emissions than conventional concrete and Portland cement. This study investigated the efficiency of geopolymers produced with short curing time and low curing temperature against gamma and neutron radiation. Ground blast furnace slag (GBFS), metakaolin and quartz powder were used as binders to produce geopolymers. In addition, 200, 400 and 800 kg/m3 quartz sand (with high SiO 2 content) was used instead of river aggregate in the mixtures. Geopolymers were cured at 40, 60 and 80 °C for 6, 8 and 10 h. The hardened unit weights of geopolymers vary between 2160–2346 kg/m3. As the quartz sand content increased, the hardened unit weight of the mixtures increased. As the curing temperature increased, the unit weight of the mixtures decreased as the evaporation increased. The compressive strength of geopolymers varies between 40.3 and 153.9 MPa, and the flexural strength varies between 3.3 and 8.8 MPa. As the curing temperature and time increase, the mechanical properties of the mixtures improve as the geopolymerization increases. In addition, if quartz sand is used instead of river sand, the compressive strength can increase up to 40%. With the increase of quartz sand content, the capillarity coefficients of geopolymers decrease. Capillarity coefficients of geopolymer mixtures are below 0.10 kg/m2.min0.5. Besides, fast neutron/photon radiation-shielding features of the geopolymers were examined, experimentally. The M3 sample is more accomplished at absorbing gamma photons due to its higher GBFS content. The M1 sample with the highest concentration of quartz sand is the most effective sample at attenuating fast neutrons and has a better Ʃ R value to some commonly used neutron attenuators. As a result, it has been shown that geopolymers with a compressive strength of about 160 MPa can be produced after 10 h. This study also revealed that M1 and M3 samples can be put to good use for protection from fast neutron and gamma-ray radiations, respectively, and new geopolymer materials can be designed as shielding materials. [ABSTRACT FROM AUTHOR]