Energy-dependent gamma attenuation analysis of BiBZnP glass-ceramics using theoretical and computational approaches.

In this study, photon shielding properties of standard concrete (SC), concrete doped ferro boron (CFB), concrete doped boron carbide (CBC), concrete doped galena (CG) and concrete doped ilmenite (CI) were investigated. A theoretical study of the mass attenuation coefficients (MAC) of standard concrete and concrete doped materials were determined by a winXCOM computer program. The radiation shielding parameters such as mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), half value layer (HVL), tenth value layer (TVL) and mean free path (MFP) of the mixture were calculated in the photon energy range of 0.01-10.0 MeV. The MAC values showed a sharp decline as the energy increases to a certain extent and reduces smoothly after that for all the materials investigated. The maximum (minimum) MAC values were 10.88 (0.023), 34.90 (0.024), 15.80 (0.022), 39. 20 (0.027), and 34.50 (0.023) cm2/g for SC, CFB, CBC, CG and CI respectively. The maximum value of LAC was obtained at 0.010 MeV with value of 44.10, 81.22, 20.40, 16.90 and 99.20 cm-1 for SC, CFB, CBC, CG and CI respectively. The MAC and LAC value are in the order of CG > CI> CFB > SC > CBC. The HVL, TVL, and MFP show similar pattern and are in the order of CBC > CI > SC > CFB > CG. The results indicate that adding galena compound into concrete mixture can significantly enhance the photon shielding capability.

Characterization of copper oxide and cobalt oxide substituted bioactive glasses for gamma and neutron shielding applications

BaO-doped Na2O–CaO–P2O5 bioactive glasses: A closer look at radiation attenuation properties for medical applications

Effect of bismuth and lithium substitution on radiation shielding properties of zinc borate glass system using Phy-X/PSD simulation

Radiation shielding performance of CeF3-Doped Li2O-PbO-GdF3-SiO2 glasses: Monte Carlo simulation MCNPX and PHY-X/PSD study.

To observe the direct effect of molybdenum reinforcement on nuclear radiation shielding properties, a detailed investigation was performed with a group of bismuth borate glasses. Accordingly, glass samples with the nominal compositions (65-x)B2O3 + 20Bi2O3 + 15Na2O + xMoO3: x = 0, 1.5, 3, 4.5, 6 and 7.5 wt% have been synthesized by the solid state conventional method. The samples were named as M0 (x = 0), M1 (x = 1.5), M2 (x = 3), M3 (x = 4.5), M4 (x = 6) and M5 (x = 7.5). Physical characteristics and gamma-photon attenuation properties of (M0-M5) glasses have been investigated via MCNPX simulation code and XCOM program. XRD patterns confirmed that M0-M5 glasses were in amorphous nature. The density of the prepared glasses increased from 4.4104 for M0 glass sample to 5.3012 gm cm−3, while molar volume decreased from 33.50083 to 28.92114 cm3 mol−1. The mass attenuation coefficient (μm) increased with the increment of MoO3 concentration in mol% and followed the order: (M0)μm < (M1)μm < (M2)μm < (M3)μm < (M4)μm < (M5)μm at all photon energies. The mean free path (MFP), half value layer (HVL), and tenth value layer (TVL) for the prepared glasses M0-M5 have the same trend and follow the order: (M5)MFP, HVL, TVL < (M4) MFP, HVL, TVL < (M3) MFP, HVL, TVL < (M2) MFP, HVL, TVL < (M1) MFP, HVL, TVL < (M1) MFP, HVL, TVL. The M5 glass sample (with maximum MoO3) achieved highest effective atomic number (Zeff)and equivalent atomic numbers (Zeq) values for all photon energy ranges (low-medium-high). Among all the glass samples, the exposure build-up factor (EBF) and energy absorption build-up factor (EABF) values for M5 glass sample with the highest MoO3 additive are minimum due to the low amount of photons accumulated. These results indicate that M5 glass sample theoretically provides maximum protection for gamma-rays among all the samples.

Gamma-ray interactions with ytterbium ions doped BLFB glasses for shielding applications

Abstract: This study examines zirconia-doped transparent glass ceramics (TGCs) based on the SiO₂–Na₂O–CaO–P₂O₅ system as potential radiation shielding materials, expanding on the initial synthesis and characterization by Mishra et al. (2024). The research specifically investigates the effects of incrementally substituting calcium oxide (CaO) with zirconium dioxide (ZrO₂) in concentrations from 0 to 6 mol%. Our work builds upon prior research by evaluating how ZrO₂ doping influences crucial radiation attenuation parameters, particularly density and structural compactness. The mass attenuation coefficients of these zirconia-doped TGCs were determined by utilizing Phy-X/PSD software and the PHITS 3.22 Monte Carlo simulation code across a photon energy range of 0.015 MeV to 15 MeV. A strong alignment was detected between the simulated results and theoretical predictions. Critical shielding parameters—including the half-value layer (HVL), tenth-value layer (TVL), linear attenuation coefficient (LAC), effective atomic number (Zeff), mean free path (MFP), and electron density (Neff)—were consequently evaluated via Phy-X/PSD software, relying on the calculated mass attenuation coefficients. The findings demonstrated that the MAC and LAC, Zeff, and Neff presented a decline in correlation with a rise in photon energy, while MFP, HVL and TVL have increased alongside the rise in photon energy. The findings demonstrate a direct relationship between increased ZrO₂ concentration and enhanced material density, reduced molar volume, and improved structural compactness, all of which contribute to better radiation shielding capabilities. Zirconia (ZrO₂)-doped transparent glass ceramics (TGCs) exhibit improved gamma-ray shielding performance, with the BG4-labeled glass ceramic displaying the highest shielding efficiency among the samples tested.

This work seeks to prepare the polyvinyl alcohol (PVA)/carboxymethyl cellulose (CMC)/polyvinyl pyrrolidone (PVP)/ nano CdS0.9M0.1, M=Cu, Co, Mn, Zn to utilize in low-cost dielectric and radiation shielding applications PVA/CMC/PVP blended polymers with the fillers. Precise phase recognition was conducted for the filler samples CdS0.9M0.1 employing the X-ray diffraction equipment. The effect of fillers on the structure and morphology of PVA/CMC/PVP blended polymer was explored. Doped blended polymers with CdS0.9Cu0.1 or CdS0.9Zn0.1 have the highest dielectric constants across the frequency ranges tested. At 1 kHz, the dielectric values for undoped and doped PVA/CMC/PVP blended polymers with CdS0.9M0.1 (M=Cu, Co, Mn, Zn) are 8.7088, 12.38172, 11.30789, 10.4688 and 12.48031, respectively. The incorporation of CdS0.9M0.1 into the host blended polymer enhanced the ac conductivity of an undoped blend. The kind of filler affected the capacitance properties of the host blended polymer. Throughout all energy ranges, the doped blended polymers exhibited higher linear attenuation coefficient (LAC) and mass attenuation coefficient (MAC) values than the undoped blended polymer, irrespective of the type of fillers used. At 15 keV, the LAC and MAC values for undoped and doped PVA/CMC/PVP blended polymers with CdS0.9M0.1 (M=Cu, Co, Mn, Zn) are (1.49677 cm−1, 1.15581 cm2 g−1), (1.6894 cm−1, 1.20646 cm2 g−1), (1.67345 cm−1, 1.19945 cm2 g−1), (1.67059 cm−1, 1.19351 cm2 g−1) and (1.69687 cm−1, 1.21047 cm2 g−1), respectively. The half-value layer (HVL) and tenth-value layer (TVL) values of the filled blends decreased as the host blend was infused with nanofillers. The FNRCS value of the host blend increased following loading with CdS0.9M0.1. The influence of dopants on the exposure building factor (EBF) and energy absorption building factor (EABF) has been considered.

In the current study, the epoxy material was mixed with 10%, and 30% weight percent carbon material as filler in different thicknesses (1 cm, 1.5 cm, and 2 cm). Transmission electron microscope (TEM) measurements showed the average size of the nano-carbon was 20 nm with a standard deviation of 5 nm. The morphology of samples was examined using scanning electron microscopy (SEM), which showed the flatness of the epoxy surface, and when the content of carbon increases, the connection between the epoxy array and carbon increases. The compression test indicates the effect of nano-size on enhancing the mechanical properties of the studied samples. To survey the shielding properties of the epoxy/carbon composites using gamma-rays emitted from Am-241, Ba-133, Cs-137, Co-60, and Eu-152 sources, which covered a wide range of energies from 0.059 up to 1.408 MeV, the gamma intensity was measured using the NaI (Tl) detector. The linear and mass attenuation coefficients were calculated by obtaining the area under each peak of the energy spectrum observed from Genie 2000 software in the presence and absence of the sample. The experimental results obtained were compared theoretically with XCOM software. The comparison examined the validity of experimental results where the relative division rate ranged between 0.02 and 2%. Also, the measurement of the relative division rate between linear attenuation coefficients of micro- and nano-composites was found to range from 0.9 to 21% The other shielding parameters are calculated at the same range of energy, such as a half-value layer (HVL), mean free path (MFP), tenth-value layer (TVL), effective atomic number (Zeff), and the buildup factors (EBF and EABF). The data revealed a consistent reduction in the particle size of the shielding material across various weight percentages, resulting in enhanced radiation shielding capabilities. The sample that contains 30% nano-carbon has the lowest values of TVL (29.4 cm) and HVL (8.85 cm); moreover, it has the highest value of the linear attenuation coefficient (LAC), which makes it the best in its ability to attenuate radiation.

Enhanced gamma radiation shielding in B2O3–Na2O–PbO–SiO2–BaO glass system: Investigating the influence of BaO

A synergistic experimental–theoretical study of radiation attenuation in locally manufactured Iraqi glasses

Three borate glass systems with chemical formula 65 B2O3 + 30 Na2O + 5 (x) wt%; x = Al2O3, MgO, and Li2O were fabricated by the common melting-annealing method and coded as BNAl, BNMg, and BNLi, respectively. XRD pattern revealed the non-crystalline form and the glassy states of the prepared samples. UV-optical absorption spectra showed UV cutoff peaks in the range 320–340 nm and optical energy gap (Eopt) by Tauc’s model (ETauc’s) and ASF method (EASF) revealed quite similar values ranged from 2.60 to 3 eV before irradiation and 2.23 to 2.60 eV after 20 kGy of gamma irradiation. Raman spectra show three detectable regions at; (i) 250–600 cm−1, (ii) 500–1000 cm−1 and (iii) 1000–2000 cm−1 correlated to different borate forms. Many radiation shielding parameters were theoretically calculated using Phy-X/PSD and simulated via Monte Carlo code (MCNP-5) in photon energy range (0.015–15 MeV). Mass attenuation coefficient (MAC), linear gamma attenuation coefficient (LAC), effective atomic number (Zeff), fast neutron macroscopic cross section (∑R), exposure buildup factor (EBF) and energy absorption buildup factor (EABF) at various penetration depths PD, as well as half (HVL) and tenth value layers (TVL) and mean free path (MFP) were also estimated. The shielding parameters showed the order of (MAC, LAC)BNAl > (MAC,LAC)BNMg > (MAC, LAC)BNLi. The stability of the glasses optical, and structural properties against gamma irradiation indicate the capable use of the glasses for radiation shielding applications specially Al2O3 glass with the heaviest atomic weight and the highest capacity for radiation shielding protection.

Flexible stretchable low-energy X-ray (30–80 keV) radiation shielding material: Low-melting-point Ga1In1Sn7Bi1 alloy/thermoplastic polyurethane composite

Photon, neutron absorption capabilities of Y2O3-Al2O3-P2O5 glasses