Determination of neutron and gamma ray shielding properties, secondary radiation formations and neutron damage of composites containing polyester/pyrite/titanium diboride.

In this work, the glass system in formula (70-x)B2O3-30TeO2-xNb2O5 at x = 0, 10, 20, 30, 40 and 50 mol% were determined gamma rays, fast and thermal neutrons shielding properties. The gamma-ray shielding properties have been explained for some parameters such as mass attenuation coefficients (mm), effective atomic number (Zeff), and half value layer (HVL). These parameters were evaluated by the WinXCom software program at energies of 10-3-105 MeV. While fast and thermal neutrons were calculated based on the macroscopic neutron capture cross-section. The results found that the addition of Nb2O5 by replacing B2O3 improved gamma ray shielding characteristics. This event also improved fast neutron shielding. Whereas, the thermal neutron found that the low Nb2O5 content was superb. These results reflected that the glass sample with high Nb2O5 content is excellent for gamma rays and fast neutron attenuation while low Nb2O5 content is excellent thermal neutron shielding glass. The results of this study are useful in enhancing the efficiency of materials for shielding gamma rays, fast and thermal neutrons.

The effect of Bi2O3 content on photon, alpha particle, proton, fast and thermal neutron shielding capacity, and elastic moduli of 10ZnO-(90-x)B2O3-xBi2O3 (ZBB-glasses): x = 25–50 mol% has been investigated. The mass density and Bi-content of the ZBB-glasses had the greatest impact on the values of mass and linear attenuation coefficients. The mass and linear attenuation coefficients values were followed the trend (ZBB25)MAC,LAC < (ZBB30) MAC,LAC < (ZBB35) MAC,LAC < (ZBB40) MAC,LAC < (ZBB45) MAC,LAC < (ZBB50) MAC,LAC. The mean free path (MFP) and half value layer (HVL) were having the same trend and opposite to which obtained in mass and linear attenuation coefficients. All the ZBB-glasses showed almost similar charged particle shielding capacity. However, ZBB50 had a comparable charged particle absorption efficiency. There was a 57% growth in fast neutron removal cross section as Bi2O3 molar concentration increased to 50% in the ZBB-glass matrix. ZBB50 possesses the highest fast neutron removal cross section among the ZBB-glasses. In terms of thermal neutron absorbing capacity, the presence of B in the glass matrix ensures that the ZBB-glasses are good thermal neutron absorption. ZBB25 has the highest thermal neutron absorption capacity among the investigated glasses. Generally, ZBB-glasses can be adopted for photon, thermal neutron, proton, and alpha particle shielding purposes. In addition, elastic (shear, longitudinal, and Young’s) moduli and Poisson’s ratio are changed significantly with the increase of Bi2O3 content mol% in ZBB-glasses.

Radiation shielding performance of recycled waste CRT glasses doped with Li2O and Y2O3: Potential applications in medical facilitates

Effect of Bi2O3 on gamma ray shielding and structural properties of borosilicate glasses recycled from high pressure sodium lamp glass

Gamma ray and neutron shielding properties of some alloy materials

In this study, the neutron and gamma radiation-shielding properties of serpentinites from the Guleman ophiolite complex were investigated, and results were evaluated in comparison with rare earth element (REE) content. The linear and mass attenuation coefficients (LAC and MAC), half-value layer (HVL), mean free path (MFP), and effective atomic numbers (Zeff) of serpentinite samples were experimentally measured in the energy range of 80.99–383.85 keV. Theoretical MAC values were calculated. Additionally, fast neutron removal cross-sections, as well as thermal and fast neutron macroscopic cross-sections, were theoretically determined. The absorbed equivalent dose rates of serpentinite samples were also measured. The radiation protection efficiency (RPE) for gamma rays and neutrons were determined. It was observed that the presence of rare earth elements within serpentinite structure has a significant impact on thermal neutron cross-sections, while crystalline water content (LOI) plays an influential role in fast neutron cross-sections. Moreover, it has been observed that the concentration of gadolinium exerts a more substantial influence on the macroscopic cross-sections of thermal neutrons than on those of fast neutrons. The research results reveal the mineralogical, geochemical, morphological and radiation-shielding properties of serpentinite rocks contribute significantly to new visions for the use of this naturally occurring rock as a geological repository for nuclear waste or as a wall-covering material in radiotherapy centers and nuclear facilities instead of concrete.

Comparative assessment of fast and thermal neutrons and gamma radiation protection qualities combined with mechanical factors of different borate-based glass systems

TeO2–B2O3–ZnO–La2O3 glasses: γ-ray and neutron attenuation characteristics analysis by WinXCOM program, MCNP5, Geant4, and Penelope simulation codes

For both the B2O3-Bi2O3-CaO and B2O3-Bi2O3-SrO glass systems, γ-ray and neutron attenuation qualities were evaluated. Utilizing the Phy-X/PSD program, within the 0.015–15 MeV energy range, linear attenuation coefficients (µ) and mass attenuation coefficients (μ/ρ) were calculated, and the attained μ/ρ quantities match well with respective simulation results computed by MCNPX, Geant4, and Penelope codes. Instead of B2O3/CaO or B2O3/SrO, the Bi2O3 addition causes improved γ-ray shielding competence, i.e., rise in effective atomic number (Zeff) and a fall in half-value layer (HVL), tenth-value layer (TVL), and mean free path (MFP). Exposure buildup factors (EBFs) and energy absorption buildup factors (EABFs) were derived using a geometric progression (G–P) fitting approach at 1–40 mfp penetration depths (PDs), within the 0.015–15 MeV range. Computed radiation protection efficiency (RPE) values confirm their excellent capacity for lower energy photons shielding. Comparably greater density (7.59 g/cm3), larger μ, μ/ρ, Zeff, equivalent atomic number (Zeq), and RPE, with the lowest HVL, TVL, MFP, EBFs, and EABFs derived for 30B2O3-60Bi2O3-10SrO (mol%) glass suggest it as an excellent γ-ray attenuator. Additionally, 30B2O3-60Bi2O3-10SrO (mol%) glass holds a commensurably bigger macroscopic removal cross-section for fast neutrons (ΣR) (=0.1199 cm−1), obtained by applying Phy-X/PSD for fast neutrons shielding, owing to the presence of larger wt% of ‘Bi’ (80.6813 wt%) and moderate ‘B’ (2.0869 wt%) elements in it. 70B2O3-5Bi2O3-25CaO (mol%) sample (B: 17.5887 wt%, Bi: 24.2855 wt%, Ca: 11.6436 wt%, and O: 46.4821 wt%) shows high potentiality for thermal or slow neutrons and intermediate energy neutrons capture or absorption due to comprised high wt% of ‘B’ element in it.

Optical properties and radiation shielding performance of tellurite glassy composites: Role of rare earth oxides

Assessment of fast and thermal neutron ambient dose equivalents around the KFUPM neutron source storage area using nuclear track detectors

Polymers doped with heavy metal oxide are proposed to shield the radiation workers from hazardous gamma-rays and neutrons originating from nuclear reactors, high-energy physics labs, medical radiotherapy units, academic research facilities etc. In this work, polymethyl methacrylate (PMMA) matrices doped with neodymium oxide were studied and an extensive evaluation of their gamma-radiation and neutron shielding ability was done. The gamma-ray shielding properties of the polymer matrices were evaluated by Hubbell and Seltzer database using XCOM. Different parameters including mass and linear attenuation coefficient, half and tenth value layer and mean free path were assessed. In addition, the neutron shielding properties were assessed from the fast neutron removal cross-sections. Gamma-ray shielding properties in terms of mean free path for photon energies 356 and 662 keV came out to be superior to the ordinary concrete and commercially available shielding glass RS 253. The polymer matricesalso have better neutron shielding properties than the commonly used neutron shields such as Boron Carbide, Polyethylene grains and ordinary concrete. The studied light-weight and flexible PMMA matrices doped with neodymium oxide can serve as protective gamma-ray and neutron shields for the personnel involved in radiation applications.

Boron nanoparticles doped with epoxy resins were synthesized and characterized using scanning electron microscopy and Fourier transform infrared spectroscopy studies. The mechanical properties, such as tensile strength and Youngs modulus, were found to be higher for 0.3% boron addition in selected composites. The gamma-ray shielding properties, such as the mass attenuation coefficient, Zeff and Zeq values, and the neutron shielding properties, such as the mass attenuation factor for both thermal and fast neutron, were studied for the selected composites. The Zeff values of boron-doped epoxy composites indicated that boron increased the Zeff values at above 1.2 MeV. The increased boron concentration in the epoxy composites decreased Zeq values for selected energy regions. The mass attenuation factor for thermal neutrons was highest in 70epoxy + 30boron. Mass attenuation factor values were compared with other radiation-shielding materials, such as concrete, water, and commercial glass. Indeed, the synthesized boron-doped epoxy composites are helpful in neutron shielding applications.

Purpose Quinoline is formed by various natural compounds, such as alkaloids from the cinchona plant, which exhibit various biological activities, and is an important building material for the development of new drugs. Quinoline can be used in anti-radiation drug development but radiation interaction properties must be determined. Material and methods In this study, six types of synthesized quinoline derivatives were used. Fast neutron removal cross-section, mean free path, half value layer and transmission number were theoretically determined by using GEometry ANd Tracking 4 and FLUktuierende KAskade simulation codes for neutron shielding. Neutron dose absorption rates were determined using the 241Am-Be fast neutron source and the Canberra NP series portable BF3 gas proportional neutron detector. Gamma radiation shielding parameters were determined by using WinXCom and PSY-X/PSD software. Additionally, the genotoxic potentials of the derivatives were assessed by using the Ames/Salmonella bacterial reversion assay. Results and conclusions Neutron shielding parameters such as removal cross-section, mean free path, half value layer and transmission number were theoretically determined for fast neutrons. To determine neutron absorption capacity of quinoline derivatives, neutron absorption, experiments were conducted. In addition, gamma radiation shielding parameters were calculated such as the mean free path (MFP), mass attenuation coefficient (µt), half value thickness layer (HVL) and effective atomic number (Zeff) in the energy range of 0.015–15 MeV. The results of the all quinoline derivatives have excellent fast neutron shielding power compared to ordinary concrete. In addition, all quinoline derivatives have been found to have the capacity to attenuate gamma radiation. Moreover, they absorb well in both types of radiation, do not cause secondary radiation, and they are genotoxically safe at the tested concentrations. This study has demonstrated that these products can be used as active ingredients for a drug to be developed against radiation.

This study investigates the interactions of rare earth elements (REEs) with gamma rays, electrons, protons, alpha particles, and neutrons, focusing on their potential in radiation shielding. The effect of incorporating REEs into concrete at varying ratios (5-30%) on shielding performance was examined. Key parameters such as mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), mean free path (MFP), and half-value layer (HVL) were calculated using GATE/Geant4 and XCOM programs. Additionally, mass stopping power, radiation yield, and fast neutron removal cross-section (FNRCS) were determined using MRCsC, SRIM, and ESTAR. Neutron shielding behaviors for fast, slow, and thermal neutrons were assessed through simulations employing plastic scintillation detector in the GATE/Geant4 Monte Carlo. Results indicate that Lu-doped concrete significantly improves shielding capability, especially for slow and fast neutrons, while maintaining comparable performance for thermal neutrons. These findings emphasize its potential as an efficient and versatile material for neutron attenuation across various energy ranges. These findings indicate that Lu-added concrete offers superior shielding performance against gamma rays and especially neutrons, making it a potential material for critical applications with high radiation exposure, such as nuclear energy and medical radiotherapy.