Mass Attenuation Coefficient Values Research Articles

Lead-free bismuth glass system towards eco-friendly radiation shielding applications

In this study, the gamma-ray photon, electron, proton, helium ion, carbon ion, thermal neutron, and fast neutron interaction parameters of the (70-x)(Bi2O3 + ZnO) + x(V2O5 + TeO2) + 20B2O3 + 6.5SiO2 + 2.5Al2O3 + 1(CeO2 + Sb2O3) glass system were estimated with the aim of assessing their radiation shielding potentials. The mass attenuation coefficients (MACs) of the glasses were estimated for photon energies between 0.015 and 15 MeV using the PHITS simulation code and XCOM software. The stopping powers of charged radiation such as electrons, protons, α-particles, and carbon ions were also estimated by Monte Carlo simulation of particle transport using PHITS. The narrow beam transmission simulated using PHITS yielded values of MAC that were not so different from those from XCOM. The MACs of B/V-ZBVSA1 vary from 0.039–90.747 cm2/g, while those of B/V-ZBVSA2, B/V-ZBVSA3, and B/V-ZBVSA4 vary from 0.035–69.724, 0.036–73.088, and 0.037–70.597 cm2/g, respectively. The HVL of the glasses varied from 0.011–2.56 cm, 0.019–3.69 cm, 0.017–3.31 cm, and 0.017–3.36 cm for B/V-ZBVSA1 – B/V-ZBVSA4, respectively The effective atomic number varied within the limits: 28.36–76.06, 19.67–67.91, 22.14–68.70, and 22.39–68.08 for BV-ZBVSA1 – BV-ZBVSA4, respectively. The stopping powers (Sp) of electrons in BV-ZBVSA1, BV-ZBVSA2, BV-ZBVSA3, and BV-ZBVSA4 were in the range 1.219–8.043 MeVcm2/g, 1.295–9.306 MeVcm2/g, 1.264–8.859 MeVcm2/g, and 1.257–8.793 MeVcm2/g correspondingly. Comparatively, the Sp of protons, α-radiation, and carbon ions follows the order: BV-ZBVSA2 > BV-ZBVSA3 > BV-ZBVSA4 > BV-ZBVSA1. Also, the value of ΣR for BV-ZBVSA1, BV-ZBVSA2, BV-ZBVSA3, and BV-ZBVSA4 was 0.1171, 0.1126, 0.1133, and 0.1103 cm−1 accordingly, while the corresponding total cross-section of thermal neutrons was 67.6227, 46.8356, 59.1179, and 56.6994 cm−1. The present glasses showed superiority in absorbing photons and neutrons compared to some existing shields and previously recommended glasses. The present glassy samples, thus, can be adopted for radiation protection purposes, among others in radiation facilities.

Artificial neural network approach for calculating mass attenuation coefficient of different glass systems

In this study, we propose an alternative approach using Artificial Neural Networks (ANN) for determining Mass Attenuation Coefficients (MAC) in various glass systems. This method takes into account the weights of glass compositions, density, and photon energy as input features. The ANN model was trained and tested on a dataset consisting of 650 data points and subsequently validated through a K-fold cross-validation procedure. Our findings demonstrate a high level of accuracy, with R2 values ranging from 0.90 to 0.99. Additionally, the model exhibits robust extrapolation capabilities with an R2 score of 0.87 for predicting MAC values in a new glass system. Furthermore, this approach significantly reduces the need for costly and time-consuming computations and experiments, making it a potential tool for selecting materials for effective radiation protection.

Developing effective gamma and X‐ray shielding materials: Thermoplastic natural rubber composites with antimony oxide

AbstractThermoplastic natural rubber (TPNR) based on polybutylene adipate terephthalate (PBAT)/natural rubber (NR) has been prepared to develop flexible radiation shielding materials by adding antimony oxide (Sb2O3). TPNR composites were prepared with a composition of NR 40% and PBAT 60%, at various loading levels of antimony oxide. The properties of the resulting composites, such as tensile strength, elongation at break, hardness, and specific gravity of TPNR composites, were investigated. Gamma‐ray shielding properties were measured under the exposure of gamma rays in the energy range of 0.223–0.662 MeV by Compton scattering technique. X‐ray shielding properties were measured with a high‐frequency digital radiography X‐ray machine at 70–120 kVp and 40 mAs. The results show that the gamma‐ray shielding properties, such as the values of mass attenuation coefficient (μm), effective atomic number (Zeff), and effective electron density (Neff) of materials, increased with increasing amounts of Sb2O3. Similar results were observed for X‐ray shielding properties. The half‐value layer (HVL) values of all samples decreased with increasing Sb2O3 content. The obtained results confirm that TPNR/Sb2O3 can be effectively used as an alternative flexible radiation shielding material.

Investigation of gamma shielding parameters of VMQ/W/TiO2 polymer composites

Vinyl Methyl Silicone Rubber (VMQ) matrix with Tungsten (W) and Titanium dioxide (TiO2) as multi-filler materials was studied with varying Tungsten content (0, 30, 50, 70 phr (parts per hundred rubber)) and investigated for gamma radiation shielding applications. The mass attenuation coefficient of VMQ/W/TiO2 composites for 80, 356 and 662 keV were obtained using XCOM database. Various radiation shielding parameters, such as the linear attenuation coefficient, half-value layer, tenth-value layer and relaxation length were evaluated using the values of mass attenuation coefficient and density. It is found that the attenuation coefficient increases with increase in filler density, whereas the HVL, TVL and relaxation length of the composites found to decrease. The mass attenuation coefficient and HVL of VMQ/70W/30 TiO2 phr are found to be 2.88 cm2/g and 0.1 cm for 80 keV gamma rays. The results confirm that the examined shielding parameters are associated with photon energies and chemical composition. Hence, the performance of VMQ/W/TiO2 rubber based composites show superior shielding properties and the experimental results are found to be better than barite at 356 & 662 keV and slightly lower than lead and barite at 80 keV.

Elucidating of the influence of tin and cadmium in the Bi–Pb alloy on its thermal and nuclear properties as a coolant in fast neutron reactors

The purpose of this research is to investigate the physical properties and shielding characteristics of prepared (Bi–Pb) and (Bi–Pb–Sn–Cd) alloys, to be used as a coolant in a liquid metal nuclear fast reactor. The physical properties density, kinetics and mechanism of melting applying the reverse Johnson–Mehl–-Avrami rule and reduced time plot were applied, showing that melting processes take place in two dimensions, enthalpy and heat capacity were measured on the other hand for the prepared alloys within the solid and liquid states, respectively. Moreover, the results indicated that the bulk density and melting temperature of (Bi–Pb–Sn–Cd) alloys are lower than (Bi–Pb) alloys. Likewise, the thermal properties of (Bi–Pb–Sn–Cd) alloys seemed more suitable applicants than that of (Bi–Pb) alloys. Additionally, eight different gamma-ray energy lines in the range 0.12178–1.40792 MeV were used to determine the mass attenuation for the alloy samples. Also, gamma radiation attenuation characteristics, the half-value layer and effective atomic number were determined using Phy-x/PSD software. Furthermore, three types of neutron energies (slow neutrons, total slow neutrons, as well as neutrons of energies greater than 0.4 eV) were used to determine the macroscopic neutron cross-sections for the prepared alloys. The calculated values of mass attenuation coefficients exhibited a very good agreement with the experimental values of those parameters. The values of neutron macroscopic cross sections at fast neutrons for (Bi–Pb) and (Bi–Pb–Sn–Cd) alloys are small, this means that there is no consequence on fast neutrons used in a nuclear breeder reactor. Finally, we may reach the conclusion that Bi–Pb–Sn–Cd alloys are a possible candidate to be used as a coolant in fast nuclear reactors, as well as it is most suitable as an outer cooling and shielding blanket vessel as well.

Photon attenuation computational software tools - A comparative study

Various photon attenuation software tools are being used widely by researchers to evaluate the radiation shielding parameters of the elements/compounds/composites theoretically. Attempts are being made by a few researchers to update and develop software tools of these kinds. However, the efficacy of these tools in terms of their comparison is yet to be explored. Thus, an attempt has been made in the present study to compare & explore the best tool among the widely used and most trusted tools, such as Phy-X, XCOM, FFAST and XMuDat photon attenuation databases, to evaluate the shielding parameters of PVA-based composites filled with bismuth and tungsten, and also for materials such as bismuth, tungsten, gold, copper, platinum, lead and barite. Careful analysis of the data obtained computationally and experimentally shows that, although the Phy-X tool provides various shielding parameters with multiple choices in the selection of energy range, it is noticed that this tool needs to be figured out for obtaining the absorption edges of the composites of interest precisely. The XCOM database provides sharp absorption edges; however, this tool gives multiple values of mass attenuation coefficients corresponding to a particular absorption edge energy. On the other hand, The FFAST tool provides sharp absorption edges along with X ray fine structure. However, the tool restricts to work with elements and compounds in the energy range 1 keV–433 keV, which limits the utilization of this tool. Furthermore, the XMuDat tool has a limiting option to work with the materials available in its library/database and provides the mass attenuation coefficient and four other parameters. However, the XMuDat provides a large number of data points, which helps to identify any minute deviation in the values of the parameters. Therefore, the present study suggests that the XMuDat tool is much more advantageous and reliable than the other tools for the detailed study of various radiation shielding parameters.

Mechanic-elastic properties and radiation attenuation efficiency of TeO2/WO3/K2O composite glass systems for nuclear and medical application

WO3 effects on neutron and ionizing radiation defending factors of ternary tellurite-based glass blocks with molecular formula 80TeO2 –(20-x)WO3 – xK2O; x = 0–20 mol% (denoted as TKW-glass) has been reported via Phy-X theoretical calculations and Geant4 simulation code. Correlations between shielding factors and kinetics properties of the investigated glasses at different photon energy have been examined. The highest values of mass (MAC) attenuation coefficient were noted at 15 keV of the examined TKW-glass materials with the values of 38.408, 44.388, 49.855, 54.872, 59.492 cm2/g for TKW-0, TKW-5, TKW-10, TKW-15, and TKW-20, respectively. Generally, these values of the TKW-glasses obey the sequence: (TKW-0)MAC< (TKW-5)MAC < (TKW-10)MAC < (TKW-15)MAC < (TKW-20)MAC. The highest mean free path (MFP) values of TKW-glasses were registered at 15 MeV with the values of 6.101, 5.591, 5.097, 4.647, and 4.302 cm for TKW-0, TKW-5, TKW-10, TKW-15, and TKW-20, respectively. The two parameters half value layer (HVL) and MFP follow the pattern: (TKW-0)HVL, MFP > (TKW-5)HVL,MFP > (TKW-10)HVL,MFP > (TKW-15)HVL,MFP > (TKW-20)HVL,MFP. The maximum values of effective atomic number (EAN) took place at gamma energy of 15 keV corresponding to 44.35, 48.86, 52.63, 55.83, and 58.58 for TKW-0, TKW-5, TKW-10, TKW-15, and TKW-20, respectively. The trend of the buildup factors was similar for all of the glass specimens. The fast neutron removal cross-section (ΣR) enhanced as WO3 content increased in the specimens. Thus, the peaked value of ΣR is 0.1059 cm−1 was noted in the TKW-20 sample. Mechanical properties, neutron and γ-rays protection parameters were observed to improve with enhanced WO3 mol% in the TKW-glasses. The current results bear their utilization for neutron and gamma protection purposes.

Investigations on tissue equivalence of selected biomaterials through radiological parameters

The objective of this work is to investigate some commonly available tissue mimicking biomaterials for imaging phantoms and different radiation therapies utilizing gamma-photons, protons, electrons and neutrons. The various interaction parameters employed in radiology like computed tomography number, buildup factor, mass attenuation coefficient, stopping power and fast removal cross-section have been computed through various software programs namely Phy-X/PSD, XCOM, SRIM and NIST: ESTAR database. The mass attenuation coefficient values obtained from the two methods i.e. Phy-X/PSD and XCOM support each other with maximum relative difference of 1%, thus validating the use of new software for biomaterials. The tricalcium phosphate and monocalcium phosphate anhydrous are found to be the best phantom material having attenuation values 0.410 and 0.319 cm2/g and computed tomography numbers 5225.3 and 2426.1 at photon energy 59.5 keV, which are in good harmony with that of enamel and cortical bone respectively. Similarly, dicalcium phosphate anhydrous/monocalcium phosphate monohydrateare appropriate biomaterials for enamel/cortical bone over useful MeV energy range for electron as well as neutron therapy.

The effect of ZnO on the structural and radiation shielding properties in borophosphate glasses

In this work, the influence of ZnO content in the structural and radiation shielding parameters of zinc borophosphate glass were studied. The glass batch was prepared by using the melt-quenching technique. The structural analyses have been carried out using XRD, Raman spectroscopy, 11B and 31P solid state MAS NMR. Density and glass transition temperature (Tg) were measurements and band gap were determined. XRD confirms the non-crystalline nature of the prepared samples. Changes in the structural characteristics with composition are associated with a replacement of BO4 by BO3 units and the replacement of PO4 phosphorous units by PO4−1 and PO4−2 units, leading to an increase of the average number of non-bridging oxygen (NBO). Density values revealed an increase of up to 43% and Tg shows reduction followed by stability with the replacement of P2O5 by ZnO. Band gap energies were measured as a function of ZnO content. Photon interaction parameters of the zinc borophosphate glasses have been investigated by the mass attenuation coefficient (MAC), half value layer (HVL), and mean free path (MFP). For radiation in the X-ray range (40 KeV), the MAC value for glass is 887% higher than for concrete and the HVL decreases almost four times, from 20 to 6 mm thickness, with the increase of ZnO content. The rise in ZnO content also improves all radiation attenuation parameters and the results reported here show that zinc borophosphate glasses present better results than ordinary concrete and is comparable to lead-based glasses. These characteristics make this glass system an excellent choice as a high-energy ionizing radiation attenuator.

Synthesis and characterization of Lead–Nickel–Boron nanocomposite for radiation shielding application

We have synthesized the Lead–Nickel–Boron (LNB) nanocomposite using Green synthesis approach for the first time. LNB is synthesized by solution combustion method using Alovera as a reducing agent. The released combustion products do not affect the environment to a greater extent resulting in less air pollution compared to that of chemical synthesis. The synthesized nanocomposite is characterized using various techniques such as PXRD, SEM, UV–Vis and FTIR spectroscopy. The non-spherical shape of the nanocomposite has been confirmed through SEM images. XRD & FTIR studies reveal the physical and chemical structure of the compound. Both experimental and theoretical approach were used to study the gamma shielding ability of the nanocomposite and its efficiency is comparable to that of pure lead. The value of mass attenuation coefficient of the LNB nanocomposite is found to be 0.44, 0.36, 0.13, 0.10, 0.06, 0.06 cm2/g for 0.276, 0.356, 0.511, 0.661, 1.173 and 1.332 MeV gamma rays. Highest attenuation coefficient and lowest HVL (half value layer-the thickness of any given material where 50% of the incident energy has been attenuated) values are observed at 0.276MeV gamma ray energy. Thus proving excellent efficiency in attenuating low energy gamma rays. It is evident from the results of high neutron absorption cross section and scattering length of value 8.5fm which is comparable to that of Lead. Thus, LNB nanocomposite has also proved to be efficient in absorbing neutrons as well as Bremsstrahlung radiation and neutron shielding efficiency is better than that of lead thus acting as a good neutron absorber. Hence, LNB nanocomposite is efficient and environmental friendly material which can absorb multiple radiations like X/Gamma rays, neutrons and Bremsstrahlung radiation.

PVC doped with Ni0.5Pb0.5Fe2O4 spinel ferrites nanoparticles: Fabrication, structural, optical, and radiation shielding properties

In this work, (Ni0.5Pb0.5Fe2O4) nano-ferrites has been prepared by a flash auto combustion technique, then new films of polyvinyl chloride (PVC) doped with x(Ni0.5Pb0.5Fe2O4) nanoparticles: x = 0 (PVC/PNF0) – 10 (PVC/PNF10) wt% have been fabricated. The nature, physical, linear optical as well as γ-ray attenuation capacity of the fabricated PVC/(Ni0.5Pb0.5Fe2O4) nanocomposites (NCs) sheets have been investigated. The crystalline state of (Ni0.5Pb0.5Fe2O4) NPs, and amorphous state of pure PVC, and PVC/(Ni0.5Pb0.5Fe2O4) films were performed by XRD measurements. The density (ρ) increased from 1.4451 to 2.613 g cm−3 for PVC/PNF0 and PVC/PNF10 sheets as the (Pb0.5Ni0.5Fe2O4) NPs content increased from 0 to 10 wt%. The direct band gap (Egapdirect) decreased from 5.259 to 2.969 eV, whereas Urbach energy (EU) increased from 0.439 to 4.812 eV. The index of refraction (n) for the fabricated films increased with increasing the concentration of (Ni0.5Pb0.5Fe2O4) NPs. The highest and lowest mass attenuation coefficient (MAC) values possessed at 0.015 and 15 MeV, respectively. The effective atomic number (Zeff) of the currently films followed the trend: (Zeff)PVC/PNF0 < (Zeff)PVC/PNF1 < (Zeff)PVC/PNF3 < (Zeff)PVC/PNF5 < (Zeff)PVC/PNF10. The half value layer (HVL) parameter possessed the trend: (HVL)PVC/PNF0 > (HVL)PVC/PNF1 > (HVL)PVC/PNF3 > (HVL)PVC/PNF5 > (HVL)PVC/PNF10. The fabricated PVC/(Ni0.5Pb0.5Fe2O4) NCs films can be used in electronic, optical, and radiation shielding applications.

Determination of X-ray and gamma-ray shielding capabilities of recycled glass derived from deteriorated silica gel

We determined the radiation shielding properties for 10CaO–xPbO–(90-x) deteriorated silica gel (DSG) glass system (x = 20, 25, 30, 35, 40, and 45 mol.%). The mass attenuation coefficient (MAC) has been estimated at photon energies of 74.23, 97.12, 122, 662, 1173, and 1332 keV using a narrow beam X-ray attenuation and transmission experiment, the XCOM program, and a PHITS simulation. The obtained MAC values were applied to estimate the half value layer (HVL), mean free path (MFP), effective atomic number, and effective electron density. Results show that the MAC value of the studied glasses ranges between 0.0549 and 1.4415 cm2/g, increases with the amount of PbO, and decreases with increasing photon energy. The HVL and MFP values decrease with increasing PbO content and increase with increasing photon energy. The recycled glass, with the addition of PbO content (20–45 mol.%), exhibited excellent radiation shielding capabilities compared to standard barite and ferrite concretes and some glass systems. Moreover, the experimental radiation shielding parameters agree with the XCOM and PHITS values. This study suggests that this new waste-recycled glass is an effective and cost-saving candidate for X-ray and gamma-ray shielding applications.

Elucidating the effect of La2O3–B2O3 exchange on structure, optical and radiation shielding improvements of Na2O–NiO–B2O3 glass

In this work, borate glass systems containing lanthanum oxide (La2O3), nickel oxide (NiO), and sodium oxide (Na2O) were prepared using the melt quenching technique by changing the La2O3/B2O3 contents. Furthermore, the structural, optical, and radiation shielding characteristics of these glasses were investigated. Optical transmittance was measured to show that all glass samples have good transparency in the visible range. Structurally, with increasing La2O3/B2O3 contents, the density increases (from 2.226 to 3.184 g.cm−3), the molar volume decreases, and the average bond density increases. Furthermore, with increasing La2O3/B2O3 contents, the refractive index and optical basicity shift toward higher values while the electronegativity decreases. On the other hand, the radiation shielding properties, such as mass attenuation coefficient and half value layer, show enhanced behaviors with further La2O3 additions. Further, we found that the HVL of the highest La2O3-containing glass samples is smaller than all commonly used radiation shielding materials. Finally, the combination of enhanced radiation shielding properties and good transparency makes the current glasses good candidates in the radiation shielding field.

Impact of BaTiO3 on the structural, optical, and nuclear radiation shielding parameters of poly(methyl methacrylate) nanocomposites as transparent shielding material

Six weight percentages (0, 2, 5, 10, 15, and 20 wt(%)) of barium titanate BaTiO3 were doped as a nanoparticle in poly(methyl methacrylate) PMMA and their optical and nuclear radiation shielding properties were investigated. The XRD patterns, FTIR spectra and SEM images confirmed that the nanocomposite films were successfully prepared. The pure PMMA sample demonstrated a significant degree of transparency, approximately 90%. The inclusion of BaTiO3 resulted in a significant reduction in the optical bandgap while maintaining a moderate transmittance level of approximately 40% at a concentration of 10 wt (%). The direct and indirect band gap energy of PMMA were decreased from 4.81 eV to 4.62 eV–1.64 eV and 1.09 eV, respectively, after doping with 20 wt(%) BaTiO3 nanoparticles. The refractive index of the investigated samples was determined using various approaches and seen to increase after nanofiller addition. Seven energy lines, from Eu-152, Cs-137, Na-22 and Ra-226 radioactive gamma ray sources, were used to deduce the gamma ray shielding parameters of the prepared samples. Also, three neutron energy ranges were used to measure the macroscopic cross-sections for the investigated samples. The results showed good agreement between measured values of mass attenuation coefficients and those calculated by WinXCOM computer program. Furthermore, the optimal weight percentage of BaTiO3 in PMMA for attenuation of all examined gamma ray energies was 10 wt (%), whereas it was 15 wt (%) for the investigated three neutron energy ranges. In other words, a novel flexible, transparent and non-toxic polymer nanocomposite shielding material is presented and the samples containing 10–15 wt(%), demonstrates improved radiation attenuation.

Compositional dependence of transparency, linear and non-linear optical parameters, and radiation shielding properties in lanthanum, iron and calcium borate glasses

In this paper, we synthesized a novel lanthanum, iron, and calcium borate glasses system by changing lanthanum oxide (La2O3)/boron oxide (B2O3) contents and investigated their structure, optical parameters, and radiation shielding characteristics. Optical absorbance and transmittance were measured, while the optical band gap values were obtained by investigating the fundamental absorption edges via Tauc's plot. Our analyses show that all glass samples show good transparency in the visible range; further, the transparency increases from 64% to 72.5% (at 600 nm) with increasing La2O3/B2O3 contents. Moreover, with increasing La2O3/B2O3 contents, the fourfold coordinated boron units (BO4) increase, the density increases, and the trigonal boron units (BO3) decrease. Furthermore, with increasing La2O3/B2O3 contents, the fundamental absorption edges shift toward higher wavelengths, and the optical band gaps decrease. Also, with increasing La2O3/B2O3 contents, the linear and non-linear refractive indices increase. These behaviors were justified by the decreased electronegativity and increased electronic polarizability values. On the other hand, the radiation shielding properties, such as the mass attenuation coefficient and half value layer, show enhanced behaviors with further La2O3 additions. The combination of enhanced radiation shielding properties and enhanced transparency makes the current glasses good candidates in the radiation shielding field.

The affinity of bentonite and WO3 nanoparticles toward epoxy resin polymer for radiation shielding

Abstract A thorough comparative analysis was conducted between pure epoxy and a novel epoxy composite that included bentonite and WO3 nanoparticles in varying ratios. This study examined five distinct novel epoxy samples (E00, EB0, EBW1, EBW2, and EBW3) to assess their radiation shielding efficiency (RSE), taking into account the addition of bentonite and WO3 nanoparticles. Furthermore, the study compared the RSE of pure epoxy with that of the novel epoxy composite. To evaluate the radiation shielding ability of the studied epoxy samples, a few radiation shielding parameters such as linear attenuation coefficient (LAC), mass attenuation coefficient (MAC), mean free path (MFP), RSE, and transition factor (I/I 0) were calculated. The RSE values of the epoxy samples were E00 (63.41%), EB0 (87.17%), EBW1 (98.26%), EBW2 (99.82%), and EBW3 (99.99%) at an energy of 0.06 MeV with 4 cm thickness. With the increase in the incident energy, the half-value layer and MFP values were increased, whereas the LAC and MAC values decreased. In conclusion, it can be stated that the sample EBW3 is more suitable among the five epoxy samples studied for attenuating the incident photon energy from 0.06 to 1.33 MeV. Noteworthily, the obtained results demonstrate that the addition of WO3 nanoparticles enhances the shielding ability of epoxy when compared to the addition of the same amount of bentonite.

Novel flexible and lead-free gamma radiation shielding nanocomposites based on LDPE/SBR blend and BaWO4/B2O3 heterostructures

In the present work, flexible lead-free radiation shielding nanocomposite films based on low-density polyethylene (LDPE)/styrene butadiene rubber (SBR) doped with BaWO4/B2O3 heterostructures (0, 5, 10, 15, and 20 wt%) were fabricated using the melt blending method. XRD patterns and FTIR spectra revealed the successful preparation of the nanocomposite films and complexation. SEM images and EDX spectra were also used to illustrate the morphology and elemental composition of the prepared nanocomposite films. Furthermore, the research results showed enhanced thermal stability of the nanocomposite films with increased BaWO4/B2O3 loading. The mass attenuation coefficient (MAC) values for LDPE/SBR+20 wt% BaWO4/B2O3 nanocomposite film improved to 0.07218 cm2/g compared to 0.06162 cm2/g for pure LDPE/SBR blend. However, a gradual increase was observed in both parameters of mean free path (MFP) and half value layer (HVL) as energy increases. Moreover, using Phy-X/PSD software, the experimental and theoretical data for MAC were compared. The dependency of the nanocomposite's effective atomic and electron numbers on BaWO4/B2O3 content was investigated. The fast neutron removal cross-section (ΣR) values were increased from 0.1081 to 0.2112 cm−1 as the BaWO4/B2O3 content increased to 20 wt%. Overall, these nanocomposite films are suitable for radiation shielding applications.

Investigation of the effect of cement type on nuclear shield performance of heavy concrete

This article studies the radiation shielding performance of three different concrete-added samples. First, the mass attenuation coefficient values of three distinct concrete materials were computed using the MATLAB code at energies ranging from 0.015 to 15 MeV, and the findings obtained were verified by theoretical WinXcom results. Half-Value Layer (HVL), Tenth-Value Layer (TVL), Mean Free Path (MFP), Effective Atomic Number (Zeff), Exposure Build-Up Factor (EBF), Energy Absorption Build-Up Factor (EABF) are the variables computed to assess available concrete samples in terms of radiation attenuation characteristics. The results demonstrated that the concrete sample with CAC possesses better gamma-radiation shielding characteristics. Concrete samples’ removal cross-sections (∑R) were obtained to analyze their ability to stop fast neutrons. Iron, aluminum, and lead-added concretes are better in terms of their density than the other types of concretes. Given the relationship between the density of the material and neutron shielding propensities, iron, aluminum, and lead-added materials are expected to better serve for shielding purposes. SRIM Monte Carlo code, as it is standard, was utilized to compute the mass stopping power (MSP) and projection range (PR) values. The concrete sample with CAC has shown better shielding properties compared to the others in the sample of the concretes having the lowest HVL, TVL, and MFP and highest ∑R. For proton and alpha particles, the concrete sample with CAC sample shows the best radiation shielding and protection properties. The concretes selected for the study are useful for shielding purposes compared to many other materials used in industry. In addition, radiation shielding concrete is cheaper than other shielding materials. It is easier to mold into different geometric shapes and is suitable for shielding from protons or alpha particles. Among the different concretes investigated in this study, it can be used for structures such as radiation oncology and nuclear medicine clinics in hospitals. Additionally, it can act as a biological shield for nuclear power plants, particle accelerators, and radionuclide laboratories, as well as other sources of radiation.

Gamma-ray-induced changes in the radiation shielding, structural, mechanical, and optical properties of borate, tellurite, and borotellurite glass systems modified with barium and bismuth oxide

This study explores the impact of different gamma-ray doses (2.5, 50, and 100 kGy) and TeO2 ratios on the structural, optical, mechanical, and radiation-shielding properties of borate glass systems modified with barium and bismuth oxide. Various physicochemical instruments were utilized to investigate these properties. The samples’ colors changed for all glasses with gamma-ray irradiation, and the color became more darkened with increasing doses. The Fourier transform infrared (FTIR) and Raman results confirmed the glass structure stability with different doses, but they offer a variation in intensity compatible with the bandgap energy results. Borate glass has the highest mechanical properties compared to the tellurite and borotellurite glass systems. Concomitantly, a gamma dose of up to 2.5 kGy enhanced the mechanical properties of all glass systems and then showed a reduction. Moreover, borate glass has the highest thermal stability compared to the tellurite and borotellurite glass, and gamma doses showed a slight variation. The tellurite and borate glasses recorded the highest and lowest band gaps, respectively. Experiments on the radiation-shielding properties and the effect of gamma doses were performed. The gamma-ray doses affected the mass attenuation coefficient (MAC) values of the tellurite and borotellurite glass samples. In contrast, the borate glass samples exhibited the highest MAC withstanding against gamma doses, and MAC values showed no variation with changing gamma doses. In summary, borate glass has the highest thermal stability, structural and mechanical properties, and stability in radiation-shielding features, which shows promise as an alternative for use in the radiation-shielding field.

Structural, physical, and radiation absorption properties of a significant nuclear power plant component: A comparison between REX-734 and 316L SS austenitic stainless steels

Abstract Austenitic stainless steels (SSs) are commonly used as in-core and surrounding structural materials in today’s industrial BWR and PWR systems. Such adaptable steels have also been the primary materials studied and used in several advanced nuclear reactor technologies, such as fast breeding and magnetic fusion reactors. In this study, some critical material properties, such as structural, physical, and radiation-shielding properties of REX-734 and 316L SS, were experimentally evaluated and compared to those of a number of other alloys. In addition to homogeneous element distribution, both alloys exhibit strong crystal orientation. The REX-734 alloy has a tensile strength of 1,259 MPa, whereas the 316L SS alloy has a tensile strength of 495 MPa. Moreover, nitrogen in the REX-734 alloy formed ultra-hard nitrides with Cr, Nb, and Si and precipitated into the structure and increased the strength. According to our findings, the mass attenuation coefficient values of the 316L SS sample were slightly higher than those of the REX-734 sample at all energies. It can be concluded that the REX-734 sample, with its exceptional strength qualities and excellent radiation attenuation capabilities, may be a viable nuclear power plant material for future investigations.