Mass Attenuation Coefficient Values Research Articles

SrO–ZnO–PbO–B2O3 glassy insights: Unveiling the structural and optical features for gamma ray shielding efficacy

The melt-quenching approach was utilised to synthesize amorphous SrO–ZnO–PbO–B2O3 glasses, with FTIR spectroscopy applied to the samples to reveal the various bonds' stretching and bending vibrations. With PbO introduced to the network, the UV–Vis absorption spectrum's absorption peak shifts towards the higher wavelength values, while Tauc plot analysis of the UV–Vis spectra reveals a 2.957–2.569 eV decrease in the band gap energy. The radiation shielding properties are examined via Phy-X program. The mass attenuation coefficient (MAC) has an inverse relation with the energy, which demonstrated the greater penetration ability of radiation that contains higher energy. In terms of the MAC values at low energies the results revealed a greater difference, while they are almost identical at higher energies. The linear attenuation coefficient (LAC) was evaluated and the chemical composition's influence discussed, with the LAC values in the order of SZPB1 <SZPB2 <SZPB3 <SZPB4. This confirms that the PbO addition leads to increased LAC values. The half value layer (HVL) decreases with increased concentration of PbO. This suggests that the higher the glass system's PbO content, the thinner the glass system needs to be to attenuate half of the incoming photons.

Investigate various shielding parameters for (C18H20O8)x (ZrSiO4)100-x and (C18H20O8)x (BiClO)100-x in medical radiological applications

This study investigates some of shielding parameters of (C18H20O8)x (ZrSiO4)100-x and (C18H20O8)x (BiClO)100-x, x=(95,80,65,50)% wt coded as (S1,S2) for medical radiation application. We employed a theoretical model to calculate a mixture’s mass attenuation coefficients (MAC) during our investigation. The XCOM computer program was utilized for this purpose within the energy range of (0.356,0.364,0.44,0.662,0.739,0.834,0.846,1.17,1.238,1.274,1.33,1.368 and 2.754) MeV. The MAC values were used to compute several parameters, such as the linear attenuation coefficient LAC, half-value layer HVL, and effective atomic number Z eff . The study’s findings revealed a consistent decrease in the value of LAC as the energy increased for all the mixtures. The maximum value of LAC is 0.366 cm−1 in energy 0.356 MeV at x=50 for S2. The results show that adding BiClO to a matrix material can greatly improve its attenuation properties and be used to protect against medical radiation. The results show that the values of Z eff decreased with increasing energies, then stabilized and changed slightly at increasing energy. The lowest HVL values and the best for shielding were in group S2. The investigation also examined the association between the Z eff and the LAC at the value of x=50. The results show the correlation was positive and strong.

Preparation and structure investigation of polyethylene terephthalate polyester reinforced Ni0.5Zn0.5Fe2O4 nanoparticles for gamma ray shielding performance

Defects of high atomic materials gamma-ray shielding such as low chemical stability, low mechanical properties, and heaviness lead us to investigate other light and flexible materials such as polymers. Polymer-doped nanosized materials are the most frequently examined materials. In this study, polyethylene terephthalate [(C10H8O4)n] was doped with Ni0.5Zn0.5Fe2O4 nanoparticles up to 40 wt% (0.0, 10.0, 20.0, 40.0 wt%) prepared by Sol–Gel auto-combustion method with the help of Gelatin. The polyester/Nanofiller composite structures were identified using x-ray photoelectron spectroscopy, x-ray diffraction, Scanning, and Transmission electron microscope as well as density measurements. x-ray photoelectron spectroscopy confirmed the successful doping of nanofiller in the polyester structure as Zn signals appear in the atomic composition and Fe signals appear in the deconvolution of the peaks. x-ray diffraction, transmission, and scanning electron microscope display the same result. x-ray diffraction graph information with the Scherer equation offered the crystal size of the composite (26 nm). Polyester/nanofiller samples were scanned against gamma-ray and experimental shielding factors were computed using a narrow beam transmission technique with sodium iodide detector and two-point sources Cs-137 and Co-60. Experimental Linear and mass attenuation coefficient values swelled as percentages of nanofiller increased in the polyester structure. Experimental Mass attenuation values were compared with theoretical ones estimated from XCOM and Physics-X programs. The difference between them does not exceed 12% which is acceptable as the x-ray photoelectron spectroscopy atomic composition utilized in the theoretical data calculation does not reveal Ni signals. This may occur at the depth of the composite structure. Finally, the half-value layer, the Tenth value layer, and the Mean free path are determined experimentally, and their values are reduced as the nanofiller doping percentage rises in the structure. This result confirms the efficiency of nanofiller addition to the polyester structure to attenuate gamma-ray.

Experimental radiation shielding, mechanical and optical properties for borosilicate glass system: Role of varying SrO

Borosilicate glass is one of the famous glasses used in labs and kitchenware since its thermal expansion is so low. This research synthesized a new group of borosilicate glass to study its mechanical, optical, and radiation shielding properties. The experimental shielding setup was set to explore the glass performance in the radiation shielding field. The results were compared with the XCOM data to check validity. The optical properties were determined using absorption spectra for glass samples. At the same time, the mechanical properties were assessed theoretically to give an impression of the glass structure. The radiation shielding experimental setup was validated with a relative difference of 9.8066% between practical and theoretical findings. Meanwhile, adding SrO instead of B2O3 increased the radiation shielding features. The mass attenuation coefficient values at 0.184 MeV rose from 0.1448 to 0.1474 cm2/g with the addition of SrO. The mechanical and optical parameters showed variation in results when SrO was added. For example, the band gap values are 3.547, 3.485, 3.675, and 3.527 eV for STBS15, STBS20, STBS25, and STBS30, respectively. The Urbach energy results are 0.183, 0.182, 0.180, and 0.173 eV for STBS15, STBS20, STBS25, and STBS30, respectively. At the same time, the Young modulus results are 94.071, 88.880, 89.207, and 86.035 GPa for STBS15, STBS20, STBS25, and STBS30, respectively. The Poisson ratio ranged from 0.284 to 0.278 for STBS15 and STBS30. The adding SrO reduced the hardness from 5.260 to 4.966 GPa for STBS15 and STBS30. Finally, the results indicate the ability to use current glasses in the radiation shielding applications.

Titanium alloys: A closer-look at mechanical, gamma-ray, neutron, and transmission properties of different grade alloys through MCNPcode application

Titanium alloys play a vital role in optimizing the effectiveness and security of nuclear reactors, strengthening structural durability, and facilitating the effective handling of nuclear waste. The aim of this study is to investigate the gamma-ray, neutron, and transmission properties of four common titanium alloys through the examination of the deposited energy amount in the liquid sodium coolant material, in relation to the mechanical properties of these alloys. MCNP (version 6.3) is utilized for designing the titanium pipes. Next, the pipes were re-designed considering the elemental mass fractions and densities of the investigated titanium alloys. Grade 26 sample is reported with the highest values of mass attenuation coefficients and the lowest HVL values among those investigated alloys. Grade 26 is reported to have the lowest TF value, whereas Grade 12 demonstrated the highest TF value. The highest Effective Removal Cross Section (ΣR, 1/cm) value against fast neutrons is reported for Grade 26. The utilization of Grade 26 sample as pipe material resulted in the lowest deposited energy amount (MeV/g) and subsequent lowest contamination in the coolant material. Out of the alloys that were chosen for analysis, it has been determined that Grade 26 exhibits the highest level of strength. It can be concluded that the Grade 26 alloy exhibits desirable characteristics for applications in nuclear technologies that require superior gamma-ray and neutron absorption properties, as well as exceptional mechanical properties. Nevertheless, it is essential to emphasize the importance for ongoing studies to enhance the existing material properties of Grade 26, with the aim of achieving improved safety and efficacy in nuclear applications.

Studies on structural, optical, thermal and low energy shielding for gamma rays for the ZSBP glasses

By employing the melt-quenching technique, the ZnO–SrO–B2O3–PbO (ZSBP) glasses have been successfully fabricated. The derivative of Absorption Spectra Fitting (DASF) method was used to study the energy band gap (Eg) of the glasses which decreases from 3.57 eV to 3.39 eV. The structural properties have been studied using the Raman spectroscopy. The glass transition temperature (Tg) decreases with increase in concentration of the lead oxide. The current study examines the radiation shielding properties at 30.80–444 keV. The addition of PbO to the glasses resulted in a proportionate increase in the mass attenuation coefficient (MAC), suggesting a diminishing tendency in radiation transmission. At 30.80 keV, the MAC values are extremely high and range from 18.06 to 21.11 cm2/g. As density rises, the half value layer (HVL) decreases. In addition, the average HVL (HVL‾) decreases. The glass thickness required to reduce the radiation intensity to 90 %, 50 %, 25 %, and 10 % of its initial value is investigated at an energy of 35.80 keV. The T90 %, T50 %, T25 %, and T10 % values are 0.0020, 0.0132, 0.0264, and 0.0439 cm, respectively. The results suggest that a greater thickness of the radiation barrier is necessary to attain the necessary degree of attenuation.

Evaluation the Shielding Properties of Various Water Equivalent Materials Using Different Calculation Methods and Monte Carlo

In this study, the linear attenuation coefficients (LAC), mass attenuation coefficients (MAC), half-value layer (HVL), and mean free path (MFP) of various materials such as water equivalent, ABS, Presage, RMI457, RW3, SW557, Epoxy, A150, Rhizophora spp., and Nylon-12 have been calculated using the Monte Carlo simulation method, EpiXS, Phy-X/PSD, and XCOM. Additionally, the fast neutron effective removal cross sections (ΣR) have been calculated using the empirical calculation method, Phy-X/PSD, MRCsC program, experimental and MNCP5 with the help of fast neutron mass removal cross sections. Among all the materials studied, Nylon-12 has the highest ΣR value. The calculated values of HVL, MFP, LAC, and MAC reveal that RW3, Epoxy, and Presage are the best materials in terms of their shielding properties, respectively.

The Hirshfeld topological surfaces, volumes, and their voids charge density interplay on radiation shielding properties: A case study of carbide-based ceramics

Transition metal carbides (TMCs) are explored for their potential as radiation shielding materials, with a focus on their γ-ray attenuation properties. These high-density materials, including WC, TaC, HfC, NbC, and VC, are evaluated across an energy range of 0.015–15.0 MeV. Notably, at low incoming photon energy (0.0150 MeV), these TMCs exhibit mass attenuation coefficients (MAC) (TMC, MAC (g/cm2)): (WC, 130.417), (TaC, 125.730), (HfC, 120.873), (NbC, 23.751), and (VC, 32.377) and effective atomic numbers (Zeff) from 22.69 to 73.68. These values surpass those of silicon dioxide (SiO2), highlighting the superior γ-ray attenuation capabilities of TMCs. TMCs exhibit a distinct trend in MAC values, with tungsten carbide (WC) consistently demonstrating the highest MAC values, making it the most efficient γ-ray attenuator. Hafnium carbide (HfC) closely follows, with tantalum carbide (TaC) exhibiting lower MAC values, while niobium carbide (NbC) and vanadium carbide (VC) display the lowest values. These differences can be attributed to variations in material composition and structure. Furthermore, the study delves into the impact of charge density within Hirshfeld voids on LAC values, revealing that as X⁴⁺ … C interactions increase due to higher charge density, LAC values rise. This fine-tuning of topological and charge density distributions within the crystal's voids offers a promising avenue to optimize these materials for enhanced radiation shielding effectiveness. Overall, this research contributes to the understanding of the potential utility of TMCs in radiation shielding applications, showcasing the interplay between crystal structure, composition, and charge distribution as key factors in determining their radiation attenuation capabilities.

Investigation of some optical, conducting and radiation shielding properties of Dy3+ ions doped boro-silicate glass systems

Three borosilicate glass samples of 25 % Si2O – 30 % Na2O – 45 % B2O3 doped with x Dy2O3 (where x = 0, 2, and 4 mol %) were prepared using the melt quenching technique. Photoluminescence spectra for glass samples were studied when excited by 350 nm in the 400–800 nm range, where emission sharply increases for samples doped with 2 % Dy2O3 (BSNDy2) at 580 nm after exposed to 30 kGy. Also, glass containing 2 % Dy photoluminescence constants, such as decay curves CIE chromaticity, was measured for all samples that gave three decay behaviors: slow, intermediate, and fast. Experimental lifetime (τexp.), color coordination (X, Y), and yellow/blue intensity ratio (y/b) beside the color correlated temperature (CCT) were determined before and after being irradiated by 30 and 60 kGy from γ ray source where the y/b ratio of BSNDy2 increase by increasing exposure to gamma doses and were >1. In addition, electrical conductivity at different temperatures was investigated as the BSNDy2 sample gave the highest conductivity and decreased by BSNDy4. Moreover, shielding parameters such as the tenth value layer, half value layer, mean free path and mass attenuation coefficient values were calculated at different gamma-ray energies via the Phy-X program, showing the highest values for MAC, Zeff, Neff, and Ceff for BSNDy4 sample. The findings showed that adding Dy2O3 to the glass gave a fortified shielding character.

Optimization radiation shielding properties of aluminum-based spinel minerals through the crystal tetrahedral and octahedral voids and their ions composition

In this research paper, we delve into the influence of crystal structure, void volumes and their ionic composition along with the atomic packing factor on the radiation attenuation properties of Al-based spinel compounds. The study investigates various Al-spinel chemical compositions explores their applications in radiation shielding. Analyzing mass attenuation coefficient (MAC) of six spinel minerals across different energy regions, we observe specific trends in scattering processes with the following sequential order: MACPleonaste > MACGahnite > MACHercynite > MACGalaxite > MACCeylonite > MACSpinel. The results demonstrated that the MAC values were influenced by the spinel chemical composition, crystal structure, and atomic arrangement in the lattice. Furthermore, the correlation between MAC values and the tetrahedral volume (Vtet), octahedral volume (Vocta), and the ratio of void volumes to the unit cell volume (R) was examined. Optimal void volumes and divalent and trivalent ion compositions were determined for different spinel minerals, leading to enhanced radiation shielding efficiency. The findings offer valuable perspectives for refining and optimization of spinel materials for use in radiation applications.

Enhancing Gamma-Neutron Shielding Effectiveness of Polyvinylidene Fluoride for Potent Applications in Nuclear Industries: A Study on the Impact of Tungsten Carbide, Trioxide, and Disulfide Using EpiXS, Phy-X/PSD, and MCNP5 Code

Background: Radiation protection is crucial in various fields due to the harmful effects of radiation. Shielding is used to reduce radiation exposure, but gamma radiation poses challenges due to its high energy and penetration capabilities.Materials and Methods: This work investigates the radiation shielding properties of polyvinylidene fluoride (PVDF) samples containing different weight fraction of tungsten carbide (WC), tungsten trioxide (WO&lt;sub&gt;3&lt;/sub&gt;), and tungsten disulfide (WS&lt;sub&gt;2&lt;/sub&gt;). Parameters such as the mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), effective atomic number (Z&lt;sub&gt;eff&lt;/sub&gt;), and macroscopic effective removal cross-section for fast neutrons (Σ&lt;sub&gt;R&lt;/sub&gt;) were calculated using the Phy-X/PSD software. EpiXS simulations were conducted for MAC validation.Results and Discussion: Increasing the weight fraction of the additives resulted in higher MAC values, indicating improved radiation shielding. PVDF–xWC showed the highest percentage increase in MAC values. MFP results indicated that PVDF–0.20WC has the lowest values, suggesting superior shielding properties compared to PVDF–0.20WO&lt;sub&gt;3&lt;/sub&gt; and PVDF–0.20WS&lt;sub&gt;2&lt;/sub&gt;. PVDF–0.20WC also exhibited the highest Z&lt;sub&gt;eff&lt;/sub&gt; values, while PVDF–0.20WS2 showed a slightly higher increase in Z&lt;sub&gt;eff&lt;/sub&gt; at energies of 0.662 and 1.333 MeV. PVDF–0.20WC has demonstrated the highest Σ&lt;sub&gt;R&lt;/sub&gt; value, indicating effective shielding against fast neutrons, while PVDF–0.20WS2 had the lowest Σ&lt;sub&gt;R&lt;/sub&gt; value. The Monte Carlo N-Particle Transport version 5 (MCNP5) simulations showed that PVDF–xWC attenuates gamma radiation more than pure PVDF, significantly decreasing the dose equivalent rate.Conclusion: Overall, this research provides insights into the radiation shielding properties of PVDF mixtures, with PVDF–xWC showing the most promising results.

Radiation Shielding Features of Glass Fiber Reinforced Cast Polyamide Using Phy-X/PSD and SRIM Software

The utilization of various materials for their nuclear radiation shielding properties has been the subject of a growing number of research and development projects. In this study, the radiation shielding characteristics of E-glass fiber reinforced cast polyamide were evaluated. E-glass is a form of glass fiber frequently utilized as a reinforcement in various composite materials to provide more durability, stiffness, and strength. Samples S1-S7 were defined according to various compositions of E-glass fiber contents (SiO2, Al2O3, B2O3, MgO, CaO, Na2O and K2O) and cast polyamide (C12H22N2O2). Within the energy range 0.015-15 MeV, the shielding parameters: Linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), half and tenth value layers (HVL, TVL), mean free path (mfp), effective atomic number (Zeff), atomic and electronic cross sections (ACS, ECS), fast neutron removal cross-section (FNRCS) and exposure buildup factor (EBF) were analyzed. E-glass fiber reinforced cast polyamide S7 (70% glass fiber content) exhibited higher values of LAC, MAC and Zeff and lower values of HVL, TVL, and mfp proving it to be a better radiation shielding material among the samples. An abrupt reduction in values of Zeff was discerned within the photoelectric absorption-dominant region, contrasted with a stable trend within the Compton scattering-dominant region, and a marginal elevation was noted in the pair production region. The maximum and minimum values of FNRCS were observed for samples S1 (10% glass fiber content) and S5 (50% glass fiber content) respectively. Hence, S1 would be the most effective material in fast neutron shielding. At 35 mfp penetration depth, the minimum EBF values belonged to S7 in lower and intermediate regions (0.015-3 MeV) whereas S1 showed the minimum values at higher energy regions (4-15 MeV). Furthermore, the mass stopping power (MSP) and projected range (PR) of the samples for alpha and proton particles were determined using SRIM-2008 codes. S7 exhibited better shielding features for alpha and proton particles with lower values of mass stopping power and projected range. The reinforcement of glass fiber in the cast polyamide has been noticed to have a significant impact on the shielding performance of polymer composites.

Gamma radiation shielding by titanium alloy reinforced by polymeric composite materials

The Ti-6Al-4V alloy (TAV) has several desirable properties, including high density, strength, low corrosion, biocompatibility, and flexibility. Based on these attractive features, we study the gamma radiation shielding capabilities of a titanium alloy TAV strengthened by polymeric composite materials. Examining the TAV alloy demonstrates discernible X-ray diffraction (XRD) peaks corresponding to specific crystallographic planes, showing its crystalline nature. The produced composites exhibit mass attenuation coefficient (μm) values that are very competitive compared to those of other shielding materials recorded in the current literature. The study results provide compelling evidence that incorporating TAV into polymeric composites has considerable promise in their effectiveness as gamma radiation shielding materials. These favorable features can be attributable to a high strength-to-weight ratio, corrosion resistance, non-magnetic properties, and biocompatibility. This work describes the photon attenuation characteristics and performance of an innovative polymer composite constructed with a matrix reinforced with four different TAV content proportions (20, 30, 40, and 50 wt%). Composite materials significantly improve μm values, particularly as their density increases, especially at lower gamma energy levels. The attributes make composites highly suitable for utilization in the fields of radiation and diagnostics, where the presence of adequate shielding is of utmost importance. At the energy level of 662 keV, the μm of the shielding material exhibited a notable increase as the amount of TAV was gradually raised, reaching 0.075 at a loading rate of 20% and significantly improving to 0.136 at a loading rate of 50%. The study reveals that the half-value layer (HVL) of composites increases with the energy level of the incoming gamma photons, indicating that the composites can attenuate low-energy gamma radiation and that higher-energy photons require larger thicknesses. The HVL also depends on the amount of material filling the polymer matrix, and its effectiveness improves as filler material increases.

Impact of the As2O3/B2O3 ratio on the structure and optical features of As2O3–NiO–Na2O–B2O3 glass

The impact of the As2O3/B2O3 ratio on the microstructure, linear and nonlinear optical parameters of nickel borate glass was carefully investigated for the As2O3–NiO–Na2O–B2O3 system. The As2O3 content of the present glass were varied from 0 to 16 mol%, while the glass modifiers of Na2O and glass intermediate of NiO were fixed at 18 and 1 mol%, respectively. Based on the structural investigations, the density increased from 2.52 gcm−3 to 2.95 gcm−3 and the molar volume increased from 27.11 cm3.mol−1 to 30.07 cm3.mol−1 with increasing As2O3/B2O3 ratios. Additionally, the presence of Ni2+ ions as NiO6 units was confirmed by the brown color originating from the absorption band observed at 421–428 nm in the optical absorbance of the studied glass. Furthermore, the Ni3+ ions do not participate in the coloring of the glass. Moreover, the fundamental absorption edges of the glass shift towards lower energy values with increasing As2O3/B2O3 concentrations, confirming the decreased behavior of the band gaps. Furthermore, the nonlinear refractive index increases with the increased As2O3/B2O3 concentrations. Additionally, the ligand field parameters of Ni cations, such as the ligand field splitting parameter and Racah parameter, exhibit opposite behaviors upon introducing additional As2O3/B2O3 ratio. A decrease in values of the ligand field splitting, while the Racah parameter exhibits increased values. The observed outcomes demonstrate a tendency of the bonds connecting the Ni ions and their ligands to possess higher degrees of ionic nature. Besides, the ionizing radiation properties for the prepared glasses were studied using online “Phy-X″ software in the energy range of 0.248–1.33 MeV. The ionizing radiation shielding invistigations showed enhanced parameters with further As2O3 additives. Where, with increasing the amount of As2O3 from 0 mol% to 16 mol%, there are increases in the mass attenuation coefficient values. Additionally, the half value layer values of the studied glass samples are lower than the values of most standard ionizing radiation shielding materials. The effective As2O3/ B2O3 ratio enhanced structure, optical and radiation shielding parameters of the present glass system, making these glasses suitable for ionizing radiation shielding applications.

Gamma radiation shielding properties of unsaturated polyester /Bi2O3 composites: An experimental, theoretical and simulation approach

Conventional gamma radiation shielding materials, such as lead and lead-based composites are heavy and hazardous to human health and the environment. This particular aspect has prompted research into alternative shielding materials. The key objective of this work is to investigate Bismuth Oxide and unsaturated polyester resin (UPR)-based polymer composite material as a radiation shielding. The investigation used a gamma spectrometer consisting of an HPGe detector and the radioactive point sources 60Co, 133Ba, and 137Cs that have energies ranging from 81 keV to 1332 keV for experimentally evaluating mass attenuation coefficient (MAC). Subsequently, the experimental results for MAC were compared with the corresponding values obtained from WinXCOM and Geant4 simulation. Our findings indicated that the mass attenuation coefficient values of experimentally investigated composites align well with the theoretical and simulated values. In addition, we examined the half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), and radiation protection efficiency (RPE) parameters. From the study, it can be inferred that lead (Pb) can be replaced by UPR+50 wt% Bi2O3 composite for low-energy gamma-ray shielding applications.

Shielding performance of metal oxide nanoparticles-doped polypropylene composites against gamma rays and neutrons exposure

This paper compares the theoretically measured attenuation parameters of a new type of nanocomposite shielding materials against γ-rays (energy range of 0.015 to 15 MeV) and neutrons (energy range of 0.0254 eV to 4.5 MeV) with the ones calculated using Phy-x/PSD and NGCal software. Nine nanocomposites (acted as shields) were made using hematite (Fe2O3) and cadmium oxide (CdO) nanoparticles-doped polypropylene (PP). The influence of various doping contents (x = 15, 30, 50, 75 wt%) on the shielding characteristics of the nanocomposites of composition (100-x)PP-(x)Fe2O3 and (100-x)PP-(x)CdO were examined. Radioactive isotopes like Am-241 (0.06 MeV), Ba-133 (0.081 and 0.356 MeV), Cs-137 (0.662 MeV), and Co-60 (1.173 and 1.333 MeV) were used as γ-ray sources. In addition, thermal (0.0254 eV) and fast neutrons (4 and 4.5 MeV) were used. The results revealed that the shielding performance of the proposed nanocomposites was significantly enhanced due to nanoscale metal-oxide doping. The mass attenuation coefficient (MAC) values of the PP sample impregnated with 75 wt% CdO nanoparticles varied from 0.768 cm2/g to 27.788 cm2/g and 0.018 cm2/g to 0.034 cm2/g at energies of 0.015 MeV and 15 MeV. Furthermore, it was observed that the values of fast neutron removal cross-sections (FNRCS) were impacted with an increase of 0.1162 cm-1 to 0.1225 cm-1. In addition, the linear attenuation factor (LAF) values improved intensely with increased CdO nanoparticle concentrations. The shield made using 75 wt% of CdO displayed the best shielding performance against high energy neutrons and γ irradiation.

Investigated mechanical, physical parameters and Gamma-Neutron radiation shielding of the rare earth (Er2O3/CeO2) doped barium borate glass: Role of the melting time and temperature

In this study, we aimed to explore the effects of CeO2/Er2O3, melting time, and temperature on the physical, radiation shielding, and mechanical properties of a glass composition. Specifically, we examined a glass composition comprising of 60B2O3-(40-X) BaO-XMO (where MO- Er2O3/CeO2 and X = 0.5,1.0,1.5 mol percentage). To assess the radiation shielding capabilities of the glass structure, we conducted theoretical evaluations including determining the mass Attenuation Coefficients (MAC), Fast Neutron Removal Cross-Section (FNRCS), and Mean Free Path (MFP). Furthermore, the study involved investigating the mechanical properties of borate glasses with CeO2 and Er2O3 doping, specifically examining Young's modulus, Bulk modulus, Shear modulus, and Longitudinal modulus. The obtained results were then compared. In order to determine the radiation shielding parameters, the Phy-X/PSD program and Geant4 simulation were utilized, covering an energy range from 0 to 10 MeV. The results indicate that there is strong agreement between the Phy-X/PSD and Monte Carlo simulation results for MAC values for glass samples. Our research suggests that these glasses have superior radiation shielding capabilities compared to commonly used materials for blocking radiation. This suggests that these glasses have great potential for use as effective shielding materials in radiation protection applications. It was observed that doping 1.5 mol% of Er2O3 in the lowest temperature and the longest time decreased the reflectivity of the gamma rays of the barium borate glass compared to the doping 1.5 mol% of CeO2.

Composition impacts of La2O3 on the structure and radiation shielding parameters of NiO–BaO–B2O3 glasses

The present study focused on studying the internal structure and radiation shielding properties of a borate glass system containing lanthanum oxide (La2O3), nickel oxide (NiO), and barium oxide (BaO). With increasing La2O3 doping the density values increase from 2.79 g.cm−3 for the La2O3-free glass sample to 3.40 g.cm−3 for the glass sample containing 10 mol% of La2O3. Based on results from studying the structure, it has been seen that the amount of BO4 content increases as the amount of La2O3/B2O3 increases. In detail, the values of N4 ratio increased from 42.46 % for the La2O3-free sample to 49.70 % for the glass sample containing 10 mol% of La2O3 (about 17 %). This result implies that the addition of La2O3 strongly converts the BO3 units to BO4 units, this result is consistent with the observed density increment. On the other hand, the values of nonbridging oxygens deteriorated from 8.18 % to 5.14 % when La2O3 was introduced, from 0.0 mol% to 10.0 mol%. Moreover, the ionizing radiation shielding studies showed improved behavior with additional La2O3 additives. Where, with increasing the amount of La2O3 from 0 mol% to 10 mol%, there is an increase in the mass attenuation coefficient (MAC) values. Also, the half value layer (HVL) values of the present glass samples are comparatively lower than the HVL of some standard ionizing radiation shielding materials. The enhanced radiation shielding properties of the present glass system make them suitable for ionizing radiation shielding applications.

Fabrication and structural, physical, and nuclear radiation shielding properties for Oxide Dispersion-Strengthened (ODS) alloys through Erbium (III) oxide, Samarium (III) oxide, and Praseodymium (III) oxide into 316L matrix

We report a comprehensive investigation on customization process of Oxide Dispersion-Strengthened alloys through Sm2O3, Pr2O3, and Er2O3 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 (Er2O3), Praseodymium oxide (Pr2O3), and Samarium oxide (Sm2O3). 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 Er2O3 compared to other reinforced oxides. The detector counting value reached its minimum level when a 5% Er2O3 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 Er2O3 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.

Exploring the radiation shielding properties of B2O3-PbO-TeO2-CeO2-WO3 glasses: A comprehensive study on structural, mechanical, gamma, and neutron attenuation characteristics

The objective of this study is to develop radiation-shielding glass materials with excellent physical properties by incorporating varying amounts of WO3 (x = 1, 3, 5, 10, 20 mol%) into 45B2O3-(20-x)PbO–30TeO2–5CeO2-xWO3 glasses. The glasses were synthesized using the melt casting method with B2O3–PbO–TeO2–CeO2 powders. Experimental measurements and theoretical calculations were performed to determine the mass attenuation coefficients (MAC), mean free path (MFP), half value layer (HVL), and effective atomic numbers (Zeff) of the glasses within the energy range of 59.54–661.62 keV. Additionally, the structural and mechanical properties of the synthesized glasses were evaluated using XRD, UV–Vis, FT-IR, and Micro-Vickers hardness techniques. XRD analysis indicated that all glass compositions formed amorphous structure. The addition of WO3 caused a decrease in the optical band gap energy values of the glasses. Moreover, the incorporation of WO3 enhanced the elasticity of the glasses by 17–21%. The hardness and fracture toughness values were also improved with the addition of 5% WO3, increasing from 3.53 to 4.14 GPa and from 1.07 to 1.14 MPa m0.5, respectively. The radiation shielding properties assessed through proton and alpha shielding characteristics, revealed that the addition of 20% WO3 to the glass composition allowed approximations of 82.8% of the MAC values of the glass doped with 20% PbO. Overall, the findings indicate that incorporating WO3 as a dopant improves the glasses' elastic and mechanical properties enhancing their radiation shielding ability.