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In an attempt to reutilize marble waste, a new approach is presented in the current study to promote its use in the field of shielding against ionizing radiation. In this study, we aimed to develop a novel and sustainable/eco-friendly lead-free radiation shielding material by improving artificial marble (AM) produced from marble waste combined with polyester by reinforcing it with bismuth oxide (Bi2O3) nanoparticles. Six samples of AM samples doped with different concentrations ( 0 % ,   5 % ,   10 % ,   15 % , 20 % , and 25 % ) of Bi2O3 nanoparticles were prepared. The linear attenuation coefficient ( L A C ) values were measured experimentally through the narrow beam method at different energies (0.0595   M e V , 0.6617   M e V , 1.1730   M e V , and 1.330   M e V ) for all samples with various concentrations of Bi2O3. Radiological shielding parameters such as half value layer ( H V L ), tenth-value layer ( T V L ), and radiation shielding efficiency ( R S E ) were estimated and compared for all the different samples. The results prove that increasing the concentration of Bi2O3 leads to the enhancement of the radiation shielding properties of the AM as a shielding material. It was observed that as the energy increases, the efficiency of the samples falls. High energy dependence was found when calculating the H V L and T V L values of the samples, which increased with increases in the energy of the incident photons. A comparison between the sample with the most efficient gamma radiation attenuation capability (AM- 25 % ), concrete, and lead was conducted, and a discussion regarding their radiation shielding properties is presented herein. The results show that the AM- 25 % sample is superior to the ordinary concrete over all the studied energy ranges, as evidenced by its significantly lower H V L s . On the contrary, lead is superior to the AM- 25 % sample over all the studied energy ranges owing to its unbeatable density as a shielding material. Overall, this new type of artificial marble has the potential to be used as a radiation shielding material at low- to medium-gamma energy regions, specifically in medical imaging and radiation therapy. [ABSTRACT FROM AUTHOR]

The current work discusses the radiation attenuation capability and different shielding characteristics of different mortar samples. The samples were prepared by replacing different percentages of fine aggregate with iron filling and replacing different percentages of hydrated lime with Bi2O3 (0–50 wt.%). The prepared mortar samples are coded as CHBFX where X = 0, 10, 30, and 50 wt.%. The mass and linear attenuation coefficient was determined experimentally using a narrow beam technique, where a high purity germanium detector, and different point gamma-ray sources (such as Am-241, Cs-137, and Co-60). The linear attenuation coefficient was also calculated using the Monte-Carlo simulation code and the online Phy-X/PSD software. The comparison of the three methods showed a good agreement in the results. The linear attenuation coefficient drops from 19.821 to 0.053 cm−1 for CHBF0, from 27.496 to 0.057 cm−1 for CHBF10, from 42.351 to 0.064 cm−1 for CHBF30, and from 55.068 to 0.071 cm−1 for CHBF50 at photon energy range from 0.015 to 15 MeV. The half-value layer thickness, tenth-value layer thickness, and mean free path of the prepared mortar composites were also calculated photon energy ranged from 0.015 to 15 MeV. The fast neutron removal cross-section of the prepared CHBFX mortar samples have values of 0.096 cm−1, 0.098 cm−1, 0.103 cm−1, and 0.107 cm−1 for the mortar samples CHBF0, CHBF10, CHBF30, and CHBF50, respectively. The results showed that the mortar sample with the highest iron filing concentration, CHBF50, provides the best protection against gamma rays and fast neutrons which could be used in the nuclear and medical fields. [ABSTRACT FROM AUTHOR]

With the use of multilayer materials such as concrete, mortar and ceramics that were fortified with PbO, WO3 and Bi2O3 nanoparticles, our study's objective was to produce a an effective photon shielding system. Experimental evaluation of the radiation shielding efficiency of two sets of samples with various thicknesses was conducted. The elemental content and morphology of the samples were corroborated by SEM and EDX studies, with ceramic samples exhibiting superior particle distribution and fewer voids than concrete and mortar specimens. The linear attenuation coefficient (LAC) was studied both experimentally and numerically using the Phy-X program, and it was found that the two sets of values were in satisfactory agreement. The values of LAC were consistently greater for samples with 30% of the selected heavy metal oxides than for those with 10%. The LAC for Cer-1 was 5.003 cm−1 at 0.059 MeV, whereas the corresponding LAC for Cer-2 was 2.123 cm−1. The LAC values were as follows: ceramics (5.003 cm−1), mortar (2.999 cm−1), concrete (2.733 cm−1), and the transmission factor (TF) examination of the multiple-layer specimens showed that the TF of the 3 cm thick multilayer sample was lower than that of the 2 cm thick sample and that both multilayer samples displayed better attenuation efficiency in comparison to single-layer specimens. The results show the possibility for employing multilayer structures with different densities, thicknesses, and sizes in suitable radiation shielding applications. [ABSTRACT FROM AUTHOR]

This study aims to investigate the impact of CeO2 content and particle size on the radiation shielding abilities of polydimethylsiloxane, also known as silicon rubber (SR). We prepared different SR samples with 10, 30, and 50% of micro and nano CeO2 and we measured the linear attenuation coefficient (LAC) for these samples. We found that the LAC of the SR increases by increasing the CeO2 and all prepared SR samples had higher LACs than the pure SR. We examined the effect of the size of the particles on the LAC and the results demonstrated that the LAC for nano CeO2 is higher than that of micro CeO2. We investigated the half value layer (HVL) for the prepared SR samples and the results revealed that the SR with 10% micro CeO2 had a greater HVL than the SR with 10% nano CeO2. The HVL results demonstrated that the SR containing nanoparticles had higher attenuation effectiveness than the SR with micro CeO2. We also prepared SR samples containing CeO2 in both sizes (i.e., micro and nano) and we found that the HVL of the SR containing both sizes was lower than the HVL of the SR with nano CeO2. The radiation protection efficiency (RPE) at 0.059 MeV for the SR with 10% micro and nano CeO2 was 94.2 and 95.6%, respectively, while the RPE of SR containing both sizes (5% micro CeO2 + 5% micro CeO2) was 96.1% at the same energy. The RPE results also indicated that the attenuation ability was improved when utilizing the micro and nano CeO2 as opposed to the micro CeO2 or nano CeO2 at 0.662, 1.173, and 1.333 MeV. [ABSTRACT FROM AUTHOR]

The purpose of this work is to study the thermal, optical, structural, and radiation-shielding features of glass system with composition 57B 2 O 3 –16SiO 2 –11BeO- (16-x) MgO- x La 2 O 3 , x = (0 ≤ x ≥ 16). The structural characteristics of glass samples are examined using XRD. This glass's molar volume decreased from 18.21 to 17.46 (cm³/mol), while its density increased from 3.213 to 5.967 g/cm³. Differential thermal analysis data were used to assess the thermal stability (ΔT) for BSLa samples. It was discovered that when the La 2 O 3 amount increased, the glass stability increased. The optical band gap (E o p t d i ) , (E o p t i n d i ) and Urbach's energy (E u) were computed using UV absorption spectra. (E o p t d i ) decrease from 4.323 to 3.816 eV and (E o p t i n d i ) decrease from 3.413 to 2.95 eV, whereas (E u) increase from 0.278 to 0.324 as a result of the changes of borosilicate's structured caused by the addition of La 2 O 3. The examined glasses may be utilized for non-linear optical applications, according to the high (n) and low metallization (M) values. The Phy-X tool was utilized to obtain (MAC), (LAC), and (Z eff) of the suggested glasses within the energies 0.015–15 MeV. The BSLa 16 sample achieved the highest values of the (MAC), (LAC), and (Z eff). Consequently, BSLa 16 is a good option for gamma-ray shielding applications. Skin depth (δ) of BSLa glasses. [Display omitted] • The ′ 57B 2 O 3 –16SiO 2 –11BeO- (16-x) MgO- x La 2 O 3 , x = 0, 2, 4, 8, and 16 mol %), glasses were prepared. • ′.Density increased from 3.213 to 5.967 g/cm³. • ′The glass stability increased. • ′ BSLa 16 is a good option for gamma-ray shielding applications. [ABSTRACT FROM AUTHOR]

Glasses with the composition 48B 2 O 3 – 13SiO 2 – 7BaO- (32-x) Na 2 O-xY 2 O 3 , (x = 0, 1, 2, 4, and 8 mol %) were synthesized by the melt quenching procedure. There is good transparency in every glass sample. The increase in density (2.825–3.894 gm/cm3) of the present glasses is what triggered the decline in molar volume (25.41–21.80 cm3/mol) and the decrease in the Boron–Boron distance (0.475–0.452 nm). The estimated values show that E opt. indi. & E opt. di are 2.317, 2.672, 2.8, 2.98 and 3.1 eV, 2.69, 2.92, 3.05, 3.25, and 3.44 eV respectively, whereas (E u ) values declined. As the Y 2 O 3 increased the refractive index (n D) increased. (n D) of the synthesized glasses using E opt. indi. & E opt. di were estimated. To find the radiation properties of the suggested glasses, the Phy-X/PSD code was employed. We concluded that the current glasses have better radiation shielding capabilities when employed in such fields. As the Y 2 O 3 replacing ratio increased ∑ R increased. • The glass system 48B 2 O 3 – 13SiO 2 – 7BaO- (32-x) Na 2 O-xY 2 O 3 , x = (0 ≤ x ≥8) in mol% was prepared. • The density increased from 2.825 to 3.894 g/cm3. • As the Y 2 O 3 replacement ratio increased the refractive increased. • The glass sample G5 exhibited the best properties. [ABSTRACT FROM AUTHOR]

W3+-doped multicomponent B 2 O 3 -SiO 2 -ZnO-Na 2 O glasses in a range of concentrations (0–6 mol %) have been manufactured using the melt quenching method. The result of replacing Na 2 O with WO 3 on the structure of zinc borosilicate glasses was examined using XRD. The density of the glass system has been determined using Archimedes' method. The substitution of Na 2 O with WO 3 in the glass composition would result in increased density and a decrease in molar volume. The incorporated WO 3 longitudinal velocities (V L m/s) increased from 4775 to 5120 and shear velocities (V S) increased from 2735 to 2955. The elastic moduli resulted in a uniform behavior when WO 3 increased, and the values ranged from 72.6 to 121.1 GPa for longitudinal modulus, 23.8–40.3 GPa for shear modulus, 40.8–67.3 GPa for bulk modulus, and 59.8–100.9 GPa for Young's modulus. The Debye temperature (θ D) increases from 431.71 to 506.33 as an increase in WO 3. Higher (θ D) indicates stronger atomic bonds and stiffer glasses. The elastic moduli based on the Makishima-Mackenzie model have been investigated. The trend indicates an increase in (Lth) varied between 137.7 and 219.1 GPa, (Gth) ranged from 38.7 to 50.3 GPa, (K) ranged from 86.16 to 152 GPa, and (Y) varied between 95.6 and 128.8 GPa, with an increase in the concentration of WO 3. The Phy-X program was used to determine the shielding characteristics for the samples, including mean free range (MFP), effective atomic number (Z eff), and neutron. Z eff increases along with WO 3 concentration and MFP decreases. The increase in the (FNRCS) due to the rise in sample density is linked to the concentration of WO 3. FNRCS (cm−1) values are 0.123 for SW 0 , 0.128 for SW 1 , 0.137 for SW 2 , 0.143 for SW 4 , and 0.162 for SW 6. It was determined that SW 6 had the best shielding capacity based on the MFP and Z eff values. This could have promising implications for various applications where radiation shielding or protection is necessary. This suggests that these glasses offer superior features that make them effective for shielding. • 21SiO 2 -13ZnO-(17-x) Na 2 O-xWO 3 (0 ≤ x ≤ 6 mol %), glasses were manufactured. • Density increases along with their WO 3 concentration. • Longitudinal velocities (V L) and shear velocities (V S) are increased. • It was determined that SW 6 had the best shielding capacity. [ABSTRACT FROM AUTHOR]