HVL Values Research Articles

Comprehensive investigation on physical, structural, mechanical and nuclear shielding features against X/gamma-rays, neutron, proton and alpha particles of various binary alloys

In this study, four alloys composed of highly pure elements (lead, zinc, tin and bismuth), named Pb–Zn50, Pb–Sn50, Sn–Zn50 and Sn–Bi50 were prepared by rapid solidification process (RSP) using melt-spun technique. The structural, mechanical properties (elastic and plastic deformations), and microhardness have been investigated and analyzed using X-ray diffraction, tensile test machine, and vickers microhardness respectively. According to results, the yield strength, ultimate tensile strength (UTS), toughness, and Vickers hardness (Hv) were improved due to the advantages of rapid solidification technology including elimination of grain boundary segregation, improvement in alloy homogeneity, refinement of grain size, formation of novel metastable crystalline, rises in the equilibrium solid solubility's of solute elements and reduction in the degree of order. This can be ascribed to reinforcement of Zn and Bi particles, refined β-Sn, Zn and Bi grains that could obstruct the dislocation slipping. In addition, the shielding performance of these alloys for gamma radiation were examined and analyzed utilizing WinXCom software over energy range 0.015–15 MeV. The alloys under study found to be good shielding materials against γ-ray relative to common shielding materials and newly studied materials. The results indicate that the Sn–Bi50 alloy has the highest values of μm, Zeff and Zeq ranging from 0.039 to 81.3 cm2/g, 60.41–73.83, and 64.02–70.793 respectively. While it has the smallest values of HVL (ranging from 8.73E-4 to 1.86 cm) which means that it is the best choice as a γ-ray shielding material. In aspects of neutron attenuation characteristics, the results also indicate that the Pb–Zn50 alloy has the highest value of ΣR (0.133 cm−1) amongst all other alloys, frequently used neutron shielding materials, and recently studied materials. Furthermore, proton (H+1) and alpha particles (He+2) projected range (PR) and mass stopping power (MSP) values have been calculated. It can be concluded that Zn–Pb alloy among the examined samples is superior in terms of shielding against proton and alpha particles. This paper provides a comprehensive examination of the use of lead and the development of new safety lead-free shielding materials in many applications including nuclear medicine.

Mathematical Calculation of X-Rays/Gamma-Rays Interaction with Zinc Bismuth Borate Glass Using Phy-x Program in Compton Energy Range

The zinc bismuth borate (ZBB)glasses have been calculated using Phy-X program at the Compton energy range. The ZBB glasses were decided in the concentration of Bi2O3 = 25, 30, 35 and 40 mol%. The mass attenuation coefficient, the effective atomic number, the effective electron density, the half value layer and the lead equivalent thickness were investigated. The results show the trend of values were decrease when the Compton energy increasing and found the values were higher when the concentration of Bi2O3 increases. The Zeff and Neff show similar trend showing that the values decrease with decrease in Bi2O3 content. The HVL value shows lowest with an increase in concentration of Bi2O3 suggesting their role to be good candidature for radiation shielding material applications. The lead equivalent thickness of glass samples shows a good trend when adding more concentration of Bi2O3 and found the highest value at 40 mol% of Bi2O3 concentration.

Measurement on the neutron and gamma radiation shielding performance of boron-doped titanium alloy Ti50Cu30Zr15B5 via arc melting technique

The significance of radiation shielding is on the rise due to the expanding areas exposed to radiation emissions. Consequently, there is a critical need to develop metal alloys and composites that exhibit excellent capabilities in absorbing neutron and gamma rays for effective radiation shielding. Low-density Ti-based alloys with controlled structural properties can be used for radiation protection purposes. The present research investigates boron-doped Ti-based alloy, Ti50Cu30Zr15B5, which is synthesized by arc melting technique, and its structural, mechanical properties, neutron, and gamma-ray transmission rate were investigated. Monte Carlo N-Particle simulation (MCNP6.2) code is used for calculating the Thermal (2.53 × 10−8 MeV) and fast (2 MeV) neutron transmission ratio (I/I0) dependent on the sample thickness. The Phy-x program is employed for calculating the gamma-ray LAC, MAC, HVL, TVL, and MFP values. The calculated neutron shielding performance parameters of Ti50Cu30Zr15B5 alloy were compared with materials in the literature. It was found that Ti50Cu30Zr15B5 alloy demonstrated impressive physical characteristics, suggesting that it can serve as a promising alloy for neutron and gamma-ray shielding applications.

An investigation of some ionizing radiation interaction parameters in selected composite scintillation materials

In this study, the interaction parameters of neutrons, charge particles and gamma rays in seven inorganic scintillation materials with densities ranged from 3.86 to 8.30 g/cm3 were theoretically examined. SRIM Monte Carlo software was used to determine the range of H + , H e + + , A u + and O − − ions in the energy range (0.01–20) MeV, Phy-X/PSD while Py-MLBUF computer programs were used to estimate gamma radiation interaction parameters in the energy range (0.02–15) MeV. The electron total stopping power and range values at energies ranging from 0.01 to 1000 MeV were calculated using the ESTAR NIST program. The fast neutron removal cross-section (FNRCS) and the macroscopic effective removal cross-section (MRCS) were calculated using the Phy-X/PSD and MRCS tools, respectively. The outcomes of this research showed that the range of H + , H e + + , A u + and O − − ions increased with decreasing sample density but decreased with increasing projectile energies; the largest range of H + is 2090 µm in the lowest density S1 sample, while the range of A u + is 5.16 µm in the same sample. The denser sample S7 had the highest stopping power and the lowest range at higher electron energies. The S1 sample had the highest calculated HVL value of 5.403 cm, while the S7 sample had the lowest calculated HVL value of 0.0008 cm. Rising sample density causes the MAC to rise, while rising gamma energy causes the MAC to decrease. The highest MAC value recorded was 107 cm2/g at 0.015 MeV in the S7 sample, and the lowest value recorded was 0.0369 cm2/g at 15 MeV in the S1 sample. For all inorganic scintillation samples at particular gamma energies, the standard deviations for the MAC, HVL and Zeff values between the Phy-X/PSD and, Py-MLBUF programs were calculated. With energy range variation, the results for Zeff for the two samples S2 and S4 appeared to be constant. Regards to the fast neutrons, the heights value’s of FNRCS, and MRCS were recorded for S7.

High transparency of PbO–BaO–Fe2O3–SrO–B2O3 glasses with improved radiation shielding properties

This study investigated the role of PbO and BaO on the optical and radiation shielding properties of PbO–Fe2O3–SrO–B2O3–BaO glass systems. Optical studies indicate that the prepared glass samples are transparent within the visible spectrum; the transparency increases marginally with increasing PbO/BaO concentrations. Furthermore, by increasing the PbO/BaO ratio, the BO4 units increase (BO3 units decrease), and the density values increase. In addition, the optical band gaps widen, and linear and nonlinear refractive indices decrease. The reductions in nonbridging oxygen were responsible for the increased band gaps and decreased refractive index behavior. Moreover, the ionizing radiation shielding studies showed improved behavior with additional PbO additives. Also, the HVL values of the present glass samples are comparatively lower than the HVL of some standard ionizing radiation shielding materials. Finally, the combination of effective radiation shielding properties and high transparency makes the current glass samples good candidates in the ionizing radiation shielding field.

Nuclear shielding characteristics of newly developed composite metal foams: Role of CeO2 addition and foam type

In present study, new composite materials which were produced by filling open-cell aluminum foams of different thickness and pore size with various additives were surveyed with respect to photon and fast neutron shielding effectiveness. The metal foam samples were prepared in two different series (A: 30 mm thick with a pore size of 2 pores/cm and B: 10 mm thick with a pore size of 16 pores/cm) according to thickness and pore sizes, and the foams were filled with different mixtures which include Epoxy(60)-B2O3(20)-CaO(20-x)-CeO2(x); (x; 0, 5, 10, 15 and 20 wt%) chemical compositions. Gamma, X-ray and neutron measurements of the produced samples were performed using Ultra-Ge detector, linear accelerator (LINAC) and BF3 neutron detector, respectively. The gamma-transmission measurements were achieved for 30.9, 59.54, 75, 81, 276, 303, 356, 384, and 662 keV photon energies using radioactive sources of 241Am, 137Cs, 133Ba. Linear Attenuation Coefficients (LAC) of the samples were figured out with the data acquired from the measurements and MAC, HVL, Zeff and Ne values were found by way of these values. The MAC, Zeff and Ne values of the samples increased with the rising in the percentage of CeO2 added to the mixture. The energy absorption (EABF) buildup factors of the composite metal foam samples were also determined for the energy range of 0.015–15 MeV at 1–40 mfp penetration depths. It was found that the A5 and B5 samples with 20% CeO2 additive had the least EABF values. Lastly, the shielding capability of the fabricated samples against fast neutrons was specified by executing equivalent dose measurements (EAD) and calculated macroscopic cross section (∑R) values. It was established that the A2 sample had the highest absorption dose rate of 49%. The largest of the theoretically calculated ∑R values belongs to the B5 sample with 20% CeO2 additive. Generally, it was concluded that the samples in the B series, which are thinner and have more pores, have better radiation attenuation capabilities.

Chemical and radiation shielding effectiveness of some heavy metal oxide glasses for immobilizing radioactive wastes

Ce/Sb/Mn different borate glass systems based PbO in concentrations of 50, 35, and 15 mol%, respectively, were prepared by the melting–annealing method. Wide chemical, structural, and radiation shielding characterizations were studied before and after 120 kGy of gamma radiation to test the possible use of glasses for immobilizing radioactive wastes. The results showed suitable density values ranging from 3.34 to 5.30 g/cm3 increased by irradiation. FTIR spectra revealed high structural stability against irradiation correlated to the trigonal BO3, tetrahedral BO4 groups, high polarizable Pb2+ ions, and the doped metal ions. Unexpectedly, the chemical durability after in situ leaching process in H2O, 0.1 N HCl, and 0.1 N NaOH for ~ 3 months revealed clear improving after irradiation e.g., enhanced by ~ 25% for Ce-lead borate glass. Scanning electron microscope (SEM) images of the glass surfaces revealed more smooth and homogenous surfaces after irradiation. Shielding parameters by Monte Carlo code (MCNP5) and Phy-X/PSD software were studied, e.g., mass and linear attenuation coefficients (MAC and LAC), effective atomic number (Zeff), radiation protection efficiency (RPE%), half and tenth value layers (HVL and TVL), and heaviness%. Comparing the shielding behavior of the three glasses revealed that Ce-lead borate glass has the highest values of LAC, MAC, Zeff, heaviness%, and RPE% and the lowest values of HVL, TVL, and MFP, referring to the best shielding efficiency. The whole study indicates the desired properties of glasses as immobilizers or containers for radioactive wastes, e.g., nuclear medicine units in hospitals, especially lead borate glass doped Ce ions.Graphical

Structural, thermal and physical properties of cesium doped molybdenum-copper-lead glass

The influence of Cs2O content on MoO3CuO-PbO2 vitreous system has been investigated. The obtained samples labeled as: S1, S2, S3, and S4 respectively, with respect to Cs2O content were synthesized by the melt-quenching method. The Cs2O addition up to S3 sample increases the hardness, density and LAC values from 3.23 to 3.52 GPa, 6.553 to 6.906 g/cm3 and 588.50 to 610.39 cm−1 respectively, and decrease the Vm, HVL and MFP values. For S4 sample, reverse trends were observed. X-ray diffraction pattern reveals the presence of amorphous structure in the S1-S3 samples but further Cs2O addition, S4 sample leading to the formation of multiple crystalline phases. The FTIR spectra indicated that the structural unit distributions of the glasses network: [PbOn], [CuOn], and molybdate species [MoO6], [MoO4]2− and [Mo2O7]2− depends on the Cs2O content. The resonance line intensity of the Cu2+ ions gradually diminishes by addition of Cs2O.

DETERMINATION OF HALF AND TENTH VALUE LAYER PRIMARY AND SECONDARY WALLS OF X-RAY ROOM IN BALI JIMBARAN GENERAL HOSPITAL

The research has been carried out on the HVL and TVL values ​​of the primary and secondary walls of the radiology installation radiology room at RSU Bali Jimbaran. The aims of this study were (1) to determine HVL and TVL values ​​on the primary and secondary walls in the x-ray room, (2) to determine the differences between HVL and TVL values ​​if the tube voltages are varied. In determining the HVL and TVL values, ​​the linear attenuation coefficient of the walls must be known. The linear attenuation coefficient was determined by measuring the wall thickness by using a caliper, and measuring the radiation dose rate before and after passing through the primary and secondary walls. The results of the analysis of the HVL and TVL values ​​on the primary wall were 1.668 cm and 5.540 cm, meanwhile on the secondary wall ​​were 1.915 cm and 6.362 cm. When the voltage was varied 40 kV, 50 kV, 60 kV and 70 kV, there was no difference in the HVL or TVL values. Based on the results of the analysis, the HVL and TVL values ​​on the primary and secondary walls have a significant average difference.

Synergistic Effect in Ionizing Radiation Shielding with Recent Tile Composites Blended with Marble Dust and BaO Micro/Nanoparticles

In this study, we investigated the impact of micro- and nano-sized barium oxide addition on the radiation-shielding properties of red clay tiles mixed with waste marble and different sizes of BaO (micro- or nanoparticles) for comparative analysis. The linear attenuation coefficients (LAC) of the prepared samples were measured using an HPGe detector between 0.060 and 1.333 MeV. Moreover, a comparison was made between the experimental micro-composites and values obtained by Phy-X software. The results revealed that the red clay/waste marble tile composites doped with nano-sized BaO demonstrated superior radiation-shielding properties compared to those doped with micro-sized BaO. At 1.33 MeV, WR-20mBaO (containing 20 wt % micro-sized BaO) and WR-20nBaO (containing 20 wt % nano-sized BaO) exhibited HVL values of 4.75 cm and 4.25 cm, respectively. The lower HVL value of WR-20nBaO indicates superior radiation-shielding performance, highlighting the potential benefits of using nano-sized BaO as a radiation-shielding additive. Our findings also demonstrated that increasing the amount of BaO deposited onto red clay mixed-waste marble resulted in improved radiation-shielding properties. Our study demonstrates that adjusting the concentration of BaO is a viable strategy for enhancing the radiation attenuation properties of red clay tiles. In addition, the addition of waste marble to the tiles enhances its mechanical properties, and it is also positively recycled in community service.

Gamma-ray, fast neutron and ion shielding characteristics of low-density and high-entropy Mg–Al–Ti–V–Cr–Fe–Zr–Nb alloy systems using Phy-X/PSD and SRIM programs

This study aimed to assess the radiation shielding properties of ten low-density high-entropy alloys (LWHEAs) using Phy-X/PSD software to analyze various shielding parameters, such as attenuation coefficients (μm and μ), mean free path (λ), effective atomic number (Zeff), and removal cross-section (ΣR), in the energy range of ▪ to ▪. A comprehensive evaluation was performed to compare the attenuation outcomes provided by HEAs with a range of shielding materials documented in the literature. The study also calculated the build-up factors (BUFs) of the alloys by using the GP-fitting interpolation method. The stopping power of the alloys against H1/He+2 ions was analyzed using the SRIM Monte Carlo code, considering total stopping power (TSP) and projected range (PR). The results indicated that HEA8 (Al3.88Cr14.95Mo27.58Nb26.71Ti13.76Zr13.11) had the best performance in terms of shielding against γ-rays, fast neutrons, and H1/He+2 ions, as it achieved the highest values of parameters such as μm, μ, Zeff, and ΣR, along with the lowest values of HVL, TVL, λ, BUFs (▪▪), TSP, and PR. On the other hand, HEA10 (Mg10.77Al11.96Mn24.35Fe24.75Cu28.17) had the lowest BUFs in both lower (▪▪) and higher (▪▪) energy regions. The order of μm for the alloys was found to be HEA5<HEA6<HEA9<HEA7<HEA10<HEA4<HEA2<HEA3<HEA1<HEA8. The study concluded that LWHEAs possess superior radiation shielding properties compared to conventional materials, making them a promising new class of materials for radiation shielding applications.

Tungsten (VI) oxide reinforced antimony glasses for radiation safety applications: A throughout investigation for determination of radiation shielding properties and transmission factors

We report the functional assessment of tungsten (VI) oxide on gamma-ray attenuation properties of 60Sb2O3-(40-x)NaPO3-xWO3 antimony glasses. The elemental mass-fractions and glass-densities of each glass sample are specified separately for the MCNPX Monte Carlo code. In addition to fundamental gamma absorption properties, Transmission Factors throughout a broad radioisotope energy range were measured. According to findings, holmium (Ho) incorporation into the glass structure resulted in a net increase of 0.3406 g/cm3, whereas cerium (Ce) addition resulted in a net increase of 0.2047 g/cm3. The 40% WO3 reinforced S7 sample was found to have the greatest LAC value, even though seven glass samples exhibited identical behavior. The S2 sample had the lowest HVL values among the glass groups evaluated in this work, computed in the energy range of 0.015–15 MeV. The lowest EBF and EABF values were reported for 40% WO3 reinforced S7 sample with the highest LAC and density values. According to the findings of this research, WO3 will likely make a significant contribution to the gamma ray absorption properties of antimony glasses, which are employed for optical and structural modification. Therefore, it can be concluded that WO3 may be treated monotonically and can be employed successfully in circumstances where gamma-ray absorption characteristics, optical properties, and structural qualities need to be enhanced.

Evaluation of X-Ray Shielding Ability of Tungsten Rubber: A GAMOS Monte Carlo Study

Against the detrimental effects of ionizing radiation, time, distance, and shielding are the three most significant protective methods. Lead is the material of choice for shielding, particularly for personal protective equipment. However, lead's density, rigidity, and toxicity are significant disadvantages. In recent years, tungsten-containing rubber (TCR) and other lightweight, flexible, and non-toxic shielding materials have emerged as viable alternatives to lead. The purpose of this study is to examine the X-ray absorption capacity of TCR material, which can serve as an alternative to lead-based personal protective equipment. Using GAMOS simulation, radiation absorption characteristics for 11 different X-ray energies ranging from 30 to 1000 keV were obtained and compared with Phy-X/PSD data. While the MFP value produced from the GAMOS code for the TCR with 100 keV energy X rays was 0.0204 cm, the Phy-X/PSD value was 0.0296 cm. The HVL value of the TCR material for X-rays with an energy of 100 keV was 0.021 cm for Phy-X/PSD and 0.014 cm for GAMOS. It has been observed to provide excellent radiation protection against X-rays in the diagnostic imaging field. By providing greater flexibility than lead shielding materials, TCR can play a crucial role in decreasing radiation exposure.

Ionizing radiation attenuation features of Cu2-II-Sn-VI4 (II=Mn, Fe; VI = S, Se, Te) quaternary semiconducting compounds

The research's essential aim is to use Phy-X/PSD software to analyze photon attenuation properties of Cu2-II-Sn-VI4 (II=Mn, Fe; VI =S, Se, Te) quaternary semiconducting compounds at photons energies between 15 keV and 15 MeV. The parameters of photon interaction, including MAC, LAC, HVL, TVL, MFP, ACS, ECS, Zf, Nf, and Cf were determined in the chosen range of energies. The software was performed at the selected photon energies to compute each sample's R, Zeq, and build-up factors. The HVL and MFP values of the samples were compared to those mentioned in the previous studies for different concretes and commercial glasses. The HVL and MFP values for Cu2FeSnSe4, Cu2FeSnTe4, Cu2MnSnSe4, and Cu2MnSnTe4, samples are lower than those of the compared concrete types commonly utilized for protection. According to data acquired from the Phy-X/PSD software, Cu2FeSnTe4 is the optimum composite for gamma-ray attenuation among the studied samples. Also, in comparison to the other examined samples, the Cu2FeSnTe4 sample showed the greatest FNRCS (fast neutron removal cross-section) value (0.117), indicating good neutron attenuation characteristics.

Comparisons of enhanced thermal neutron‐ and gamma‐shielding properties in UHMWPE composites containing surface‐treated Sm2O3 and Gd2O3 particles

AbstractThe rapid development and broad utilization of nuclear technologies has raised safety concerns, especially for those requiring radiation‐shielding equipment. To cope with such high demands and risks, the current study investigated the potential of utilizing ultra‐high‐molecular‐weight polyethylene (UHMWPE) composites containing varying contents of surface‐treated samarium oxide (Sm2O3) or gadolinium oxide (Gd2O3) particles as dual thermal neutron‐ and gamma‐shielding materials. The results showed that the thermal neutron‐ and gamma‐shielding abilities of the composites increased with increasing filler contents, as evidenced by the highest values of μ (in the case gamma rays), ∑t (in the case of thermal neutrons), and μm, as well as the lowest values of HVL and TVL, being achieved in the samples containing 25 wt% Sm2O3 or Gd2O3 (the maximum content investigated). Furthermore, based on the comparative thermal neutron‐shielding properties of the current composites to those of a common shielding product containing 15.9 wt% B2O3 (corresponding to 5 wt% B), the addition of 2.5 wt% Gd2O3 or 4.8 wt% Sm2O3 to the UHMWPE matrix was sufficient to attenuate thermal neutrons with equal efficiency to that of the referenced material. Furthermore, the results indicated that the addition of both fillers increased the density and hardness (Shore D) but reduced the degree of crystallinity, tensile strength, elongation at break, and dielectric strength of the composites, for which the degree of changes in each property largely depended on filler types and contents. In summary, the overall results suggested that both Sm2O3 and Gd2O3 could substantially enhance the thermal neutron‐ and gamma‐shielding properties of the composites, while the developed UHMWPE composites offered durability and excellent electrical properties that could be suitable for use in various applications.

Investigation of photon interaction parameters of alloys used in orthodontic treatments for dental radiology applications

In the present study, it was aimed to examine the photon interaction parameters of some alloys used in orthodontic treatments in dental and medical radiology energies. First of all, a transmission geometry consisting of 241Am (100 mCi) radioactive source and Ultra Ge detector was established to experimentally obtain the mass attenuation coefficients (μρ, cm2/g) of Beta Titanium (BT), Copper NiTi, NiTi (Nitinol) and stainless steel (SS) alloys, which are frequently used as orthodontic wires. The experimental μρ values in the energy range of 13.9–59.54 keV with the data obtained from the spectra were compared with the theoretical results generated with the EpiXS program. The μρ values at 59.54 keV were 0.760, 0.933, 0.924 and 1.315 cm2/g for BT, NiTi, Copper NiTi and SS, respectively. Based on μρ values, HVL and Zeff values were also obtained. The HVL values for BT, NiTi, Copper NiTi and SS at 59.54 keV were calculated as 0.203, 0.135, 0.138, 0.066 cm, respectively. Then, the buildup factor values of the alloys in the energy range of 0.015–15 MeV were calculated at penetration depths of 1–15 mfp. When all the results are evaluated together, SS is more effective in absorbing photons, while BT is the alloy with the highest photon buildup among the alloys studied. Besides, it is noteworthy that the alloys cause secondary scatterings. The data obtained from this study will provide information about the photon interaction parameters of orthodontic wires in dental and medical radiology applications.

Elaboration of X-ray shielding of highly barite-loaded polyester concrete: structure, mechanical properties, and MCNP simulation

Various research has been done in manufacturing and designing different types of radiation shielding. In this study, lead-free polymer composite panels with new special formulations have been prepared and characterized to prevent radiation leakage in medical facilities at the diagnostic energy range (60 – 120 keV). Polyester resin is used as a binder along with large amounts of mineral barium sulfate (barite) aggregate (more than 70 % by weight). SEM micrographs showed a homogeneous distribution of barite particles. Then the effects of adding barite on the physical, mechanical, and thermal properties of composite panels were investigated. The results showed that increasing the percentage of barite powder in the formulation, with the high wetting capability of polyester resin, improved physical and mechanical properties. The composite panel containing 80 wt% of barite had the highest tensile and flexure strength. Also the thermal stability of the composite panel containing 90 wt% of barite was 40 °C to 50 °C more than other samples. The samples' mass attenuation coefficient (μm) was calculated experimentally and theoretically using MCNP-5 simulation software and the XCOM program. Experimental and calculated results have been compared and were found to be in reasonable agreement. In general, with increasing barite content, the composite shielding panel became denser and μ increased while HVL and TVL values decreased. In addition, the studied shields were superior to lead by virtue of their non-toxic nature and will be a radiation shielding solution in making wall panels.

Structure and gamma-ray attenuation capabilities for eco-friendly transparent glass system prepared from rice straw ash

The current study investigates the physical structural and radiation shielding capabilities of a newly developed glass system incorporating silica extracted from rice straw ash (RSA). The purity and chemical composition of the silica are determined using XRF. XRD confirms the amorphous character of the synthesized glass. Moreover, molar volume, optical parameters, and density will be investigated. Gamma (γ)-rays shielding parameters like half-value layer, mass attenuation coefficient, the effective atomic number, and the mean free path are experimentally measured across a broad range of gamma-ray energies (81 keV–1408 keV) emitted from 152Eu, 133Ba, 137Cs, and 60Co radioactive isotopes. The exposure buildup factor will be evaluated with the geometric progression fitting approximation. In addition, Phy-X/PSD software is used to calculate theoretically the former shielding parameters. A good agreement between theoretical and experimental values has been revealed. Finally, a comparison was made to investigate the potential use of our glass to replace the common shielding material like concrete (ordinary and hematite-serpenite), commercial glass (RS 253), and the newly developed Ag2O doped boro-tellurite glass. The newly prepared glass has higher MAC, Zeff values and lowered HVL and MFP values. These properties make our prepared glass system superior in terms of shielding from γ-rays.

Radiation shielding properties of low-density Ti-based bulk metallic glass composites: a computational study

Bulk metallic glasses (BMGs), a new class of structural and functional materials with unique physical and chemical features like high corrosion resistance, high yield strength, low elastic modulus, and transparency to visible light, indicate they could be potential shield against unwanted radiations. This study presents an attempt to investigate radiation shielding efficiencies of a few titanium (Ti)-based BMGs with low densities of range 4.43–5.15 g/cm3. Different shielding properties viz., attenuation coefficients (μ m and μ), half and tenth value layers (HVL and TVL), mean free path (λ), effective atomic number (Zeff), buildup factors (EBF and EABF), and fast neutron removal cross-section (Σ R ) were evaluated in 0.015 − 15 MeV energy range using Phy-X/PSD software. The interaction of charged particles (i.e., H1 and He+2 ions) with BMG samples was investigated in terms of mass stopping power (MSP) and projected range (PR) by deploying Monte Carlo-based SRIM software. The five-parametric geometric-progression (G-P) fitting method was employed to calculate EBF and EABF, whereas Zeff values were calculated through atomic to electronic cross-section ratio. Further, obtained results were compared with two conventional shielding materials: lead (Pb) and heavy concrete (StMg). We found that among 8 BMGs, sample Ti41.9Zr36.3V12.1Cu6.3Be3.4(S1) with the lowest Ti and highest Zr-composition by mass (41.9% and 36.3%, respectively) exhibited the best gamma-rays, fast neutrons, and H1/He+2 ions shielding characteristics with the highest μ m (0.02–15 MeV), μ (0.015−0.2 MeV), Zeff (0.015–0.06 MeV) and Σ R . These values were higher than that of StMg, but lower than those of Pb. Moreover, S1 exhibited the lowest values of HVL, TVL, and λ in 0.015 − 0.2 MeV region for gamma-rays and also has the lowest MSP and PR values for H1/He+2 ions. However, the lowest EBF and EABF values belonged to BMG S1 in intermediate energy region (0.1−2 MeV) only. But, the sample Ti90Al6V4(S7) was the worst among all BMGs and StMg. Thus, low-density Ti-based BMGs have better performances towards gamma-rays, fast neutrons, and H1/He+2 ions shielding and hence the potential to replace conventional StMgs and toxic Pb-based materials.

Analyses of Gamma and Neutron Attenuation Properties of the AA6082 composite material doped with boron carbide (B4C)

Aluminum Alloy AA6082 + (0–40%) B4C materials were analyzed in the energy range between 0.015 and 15 MeV by PSD software. The mass and linear attenuation coefficients (MAC, LAC), tenth-half value layers (TVL, HVL), mean-free path (MFP), effective atomic number (Zeff), equivalent atomic number (Zeq), fast neutron removal cross-section (FNRC), electron density (Neff), effective conductivity (Ceff), and exposure buildup factors (EBFs) parameters were computed for the energy range between 0.015 and 15 MeV. The research implied that LAC and MAC values in the Aluminum Alloy AA6082 functionally graded composite materials increased with the reduction in the B4C contents in the studied material. EBFs under the penetration depth of up to 40 mfp in the energy range between 0.015 and 15 MeV were computed by employing the Geometric-Progression method. TVL, FNRC, Ceff, and Neff values varied between 0.01 and 0.452 cm, 7.918–10.527 cm-1, 5.47.1010–8.31.1010 S/m, 2.90.1025–4.34.1025 electrons/g, respectively. AA6082 material showed the maximum photon shielding performance owing to having the lowest TVL and HVL values, and the highest Zeff and MAC values while AA6082 + 40% B4C material showed the maximum neutron shielding performance because of its higher density.