Search

Radiation and nuclear technologies have side effects in addition to their important applications, so appropriate shields must be used to protect users and the public from high doses as a result of exposure to this radiation. In this work, the attenuation coefficients for polyester composites doped with waste iron filings (IFs) were studied. Six samples of different IF concentrations were manufactured, namely, Poly, Poly-IF20, Poly-IF30, Poly-IF40, Poly-IF50, and Poly-IF60 (where Poly-IF60 represents 40% polyester and 60% IF). We measured the attenuation factors using high purity germanium (HPGe)-detector along with three radioactive sources 241Am (emitting energy of 0.06 MeV), 137Cs (emitting energy of 0.662 MeV), and Co-60 (emitting energy of 1.173 and 1.333 MeV). We compared the linear attenuation coefficient (LAC) obtained by theoretical (i.e., XCOM software) and experimental (i.e., HPGe-detector) approaches for the prepared polyester composites at various photon energies (0.060, 0.662, 1.173, and 1.333 MeV). The greatest difference between the LAC values of the samples occurs at 0.060 MeV, where the Poly-IF60 sample has a much greater LAC than the other shields, followed by the Poly-IF50 sample, Poly-IF40 sample, and so on until the pure polyester shield. Specifically, their values are equal to 0.245, 0.622, 0.873, 1.187, 1.591, and 2.129 cm−1 for Poly, Poly-IF20, Poly-IF30, Poly-IF40, Poly-IF50, and Poly-IF60, respectively. We calculated the transmission factor (TF) and the radiation shielding efficiency (RSE), and found that the TF for Poly-IF30 is equal to 28.82%, 77.94%, 82.75%, and 83.75% at 0.060, 0.662, 1.173, and 1.333, respectively, while its RSE is equal to 82.57%, 24.00%, 18.80%, and 17.72%, respectively. The fast neutron removal cross-section (FNRC) of the polyester samples was calculated and the values increase when more Ifs are added to the samples. More specifically, the FNRC values are equal to 0.095, 0.100, 0.103, 0.107, 0.110, and 0.113 cm−1 for Poly, Poly-IF20, Poly-IF30, Poly-IF40, Poly-IF50, and Poly-IF60, respectively.

The investigation in this article focused on the role of La2O3 on the optical, physical, and radiation protection performance of La2O3-based glasses in the form 21.5SiO2-58.5B2O3-(20−x)ZnO:xLa2O3, where x , ( 0 ≤ x ≤ 10 ) mol%. The melt-quenching process was used to synthesize the glasses under study. Density results increased from 3.174 to 4.754, the values of the ( E opt. indi ) increased from 2.996 to 3.313 and ( E opt. di) increased from 3.364 to 3.689. Several radiation shielding factors have been evaluated to study the attenuation abilities of the ZBSL glasses and for all of them, there is a positive correlation between the mean free path (MFP) values and the incoming photon energy. The effective atomic number, Zeff, values increased for all the energies when La2O3 was employed in place of ZnO. Therefore, of all the competing shielding glasses and regular concrete, ZBSL10 glass is an excellent choice for shielding applications from gamma rays and neutrons. This study should be very beneficial for the design of these glasses or for the fabrication of new glasses for radiation protection. [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]