Mass Attenuation Coefficient Values Research Articles

Effect of WO3 on the radiation shielding ability of TeO2–TiO2–WO3 glass system

Abstract In this study, glass composition based on tungsten oxide (WO3) doped tellurium, titanium glasses: (100 − x − y) TeO2–xTiO2–yWO3: where (x = 5) and (y = 5, 10, 15, 20, 25) coded as TT5W5, TT5W10, TT5W15, TT5W20, and TT5W25 were investigated for shielding properties against ionizing radiation. Gamma radiation shielding parameters such as mass attenuation coefficients (MAC) are calculated through MCNPx code and Phy-X/PSD software in the energy range of 0.015–15 MeV. Obtained MAC values are then used to calculate other gamma radiation shielding parameters such as mean free path (MFP) and effective atomic number (Z eff). Besides this, the exposure buildup factor (EBF) was also calculated by using EXABCal software at different penetration depths (PDs) in the energy range of 0.015–15 MeV. Sample TT5W25, which has a larger WO3 content of 25 mol% shows higher values of MAC and lower values of MFP among all the examined glass samples. Our investigated TeO2–TiO2–WO3 glass samples possess the lowest MFP values in comparison with the different types of concretes and commercially available shielding glasses. In addition, fast neutron shielding characteristics in light of fast neutron removal cross-section have also been computed. Glass sample TT5W25 possesses the higher values of fast neutron removal cross-section as compared to the other glass samples. The results indicate that the adding up of WO3 improves shielding against the fast neutron and gamma radiation.

Synthesis of Novel Li2O-CuO-Bi2O3-B2O3 Glasses for Radiation Protection: An Experimental and Theoretical Study

Glass samples were synthesized according to 10Li2O + 20CuO + xBi2O3 + (70 − x)B2O3, where x = 0, 10, 20, 30, 40 mol% by the melt-quenching method. The ability of the prepared glass to protect against gamma rays and neutrons was examined experimentally and theoretically. The mass attenuation coefficient (MAC) was calculated experimentally at energies of 0.662, 1.173, and 1.333 MeV using 137Cs and 60Co sources. The obtained results were compared with the theoretical ones using a Phy-x/PSD software program version 0.1.0.0. It was found that the experimental and theoretical results are very agreed upon. Moreover, other nuclear radiation shielding parameters were evaluated. The results showed that the addition of bismuth oxide leads to an improvement in the ability of the composite glass to attenuate gamma rays by increasing the values of MAC and Zeff, while it led to a decrease in the HVL and MFP, as well as the EBF and EABF. The results also showed that the addition of copper oxide led to an improvement in the ability of the present glass to slow down fast neutrons. Sample BiS40 showed the best result for gamma ray attenuation and sample BiS10 gave the best result for fast neutron removal cross section. The results were compared with some materials used for gamma ray shielding and fast neutron removal cross section, and it was concluded that samples Bi40 and BiS10 outperformed all commercial materials.

A Study on the Gamma-ray Attenuation coefficient Parameters for Potassium Carbonate

The linear attenuation coefficient (LAC) and mass attenuation coefficient (MAC) are most important while studying of radiation, radio-isotopes in dosimentry and irradiation of materials. In the present work to calculate linear attenuation coefficient (LAC) and mass attenuation coefficient (MAC) values of different salts samples by using Gamma-ray spectrometry with Photo-Multiplier Tube (PMT) and Multi-Channel Analyzer (MCA). The 0.123, 0.511, 0.662, 1.17, 1.28 and 1.33MeV gamma energy rays used for the experiment in the interaction of Potassium carbonate salt samples and compared the Mass attenuation coefficient (MAC) values of salt samples. The obtained gamma-ray spectra were analyzed using computer software.

Investigation of radiological properties of imaging agents used in nuclear medicine with different methods and GATE/Geant4 simulation program

This study aims to determine the radiological properties of various radiopharmaceuticals used in nuclear medicine. In the study, mass attenuation coefficient values in different energy ranges were obtained for six different radiopharmaceuticals dimercaptosuccinic acid, diethylenetriamine pentaacetate, mercaptoacetyltriglycine, hexamethylpropyleneamine oxime, methoxyisobutylisonitrile, methylene diphosphate by using GATE simulation program, XCOM and WinXCom programs. Using these values, effective atomic number and electron density values were calculated with the help of the direct method, interpolation method, Auto-Zeff software, Phy-X/ZeXTra, XMuDat program, and Mayneourd's formula. In addition, the effective atomic number and electron density values obtained were compared for each radiopharmaceutical, both among themselves and between the methods. When radiopharmaceuticals were compared among themselves in low and high-energy regions, the highest effective atomic number values were obtained in dimercaptosuccinic acid, methylene diphosphate, and mercaptoacetyltriglycine. The mass attenuation coefficient values calculated using the GATE code indicate that it is a suitable method for determining the mass attenuation coefficient for imaging agents with no experimental values. This study indicates that the simulation geometry method is suitable to be used as an alternative method for the experiments. In addition, the values obtained for these molecules used as radiopharmaceuticals were examined for the first time.

Synthesis, physical, optical and gamma radiation shielding capacities of novel mercuric-sodium-lead-borate glasses

The influence of mercuric oxide (HgO) on structural, physical, optical, and radiation shielding capacities of newly developed glasses with nominal compositions (55-x)B2O3·10SrF2·25PbO·10Na2O·xHgO: x = 0, 2, 4, 6, and 8 mol% has been investigated. Hg-glasses were synthesized by the traditional melt quenching technique and coded as Hg0, Hg2, Hg4, Hg6, and Hg8, respectively. The amorphous nature of Hg-glasses was confirmed via XRD measurements. Density of the prepared glasses was measured via Archimedes' method and it was increased from 4.59 g/cm3 for Hg0 sample to 5.20 g/cm3 for Hg8 sample. The values of optical band gap (Eg) were reduced with the insertion of HgO in Hg-glass network. The direct (Eg) was changed from 3.52 to 3.21 eV, while the indirect one change from 2.47 to 2.14 eV. Urbach's energy (Eu) was varied from 0.737 to 1.544 eV and refractive index was improved from 2.197 to 4.077 at wavelength λ=500 nm. The average oscillator strength (So) of Hg-glasses was changed from 2.885×10-5 (nm)2 to 11.078 × 10−5 (nm)2. The Hg8 glass possessed the maximum values of mass attenuation coefficient (MAC)Phy-X/PSD among all Hg-glasses. The values of (MAC)Phy-X/PSD at (0.015 MeV, 15 MeV) were (0.037, 53.675), (0.38, 58.123), (0.039, 62.352), (0.40, 66.376), and (0.40, 70.210) cm2/g for Hg0, Hg2, Hg4, Hg6, and Hg8 glasses, respectively. The variation of the effective atomic number (Zeff)Phy-X/PSD of the prepared Hg-glasses has a similar trend of (MAC)Phy-X/PSD. The half value layer (HVL)Phy-X/PSD for various samples followed the trend; ((HVL)Phy-X/PSD)Hg0 > ((HVL)Phy-X/PSD)Hg2 > ((HVL)Phy-X/PSD)Hg4 > ((HVL)Phy-X/PSD)Hg6 > ((HVL)Phy-X/PSD)Hg8. However, the reduction of (HVL)Phy-X/PSD with increasing HgO concentration in the glassy system increase its ability to shield against the incident photons. The prepared Hg-glasses with improved physical and optical properties can be used in various optical applications and are superior as radiation shielding materials than seven kinds of concrete OC, HSC, ILC, BMC, IC, SSC, SMC, and RS-253-G18 glasses.

The effect of fluorine replacement on the physical properties of oxyfluorotellurite glasses TeO2-Li2O-ZnO-ZnF2

Oxyfluorotellurite glasses in the composition 65TeO2–15Li2O-(20-x)ZnO-xZnF2 (x = 0, 5, 10 mol%) were prepared by melting quenching technique and their physical, thermal and structural properties were investigated. The results showed that the density and the oxygen packing density values decrease with increasing x. By the differential scanning calorimetry, the crystallization kinetic for each sample was evaluated and showed that activation energy decreases with increasing x, which can be related to the exchange of simple Te-O bonds for Te-F bonds. The variation on the quantity of these bonds were confirmed by FTIR and Raman spectroscopy. The mass attenuation coefficient values were found to reduce exponentially with increasing the energy. The radiation protection efficiency of glasses with 10 mm was 100, 50, and 30% for X-ray (40 KeV), 60Co (2.5MeV), and 137Cs energy lines (284 KeV & 66 KeV), respectively.

Assessment of mechanical and gamma ray shielding capability of highly dense PbO-TeO2-CdO glasses

The highly dense PbO-TeO2-CdO glasses have been fabricated by the melt quenching procedure. The prepared samples are light yellow in colour and are highly transparent. The density of the samples is very high and it lies in the range of 5.576–6.082 g/cm3. The molar volume is showing downtrend from 35.488 to 33.705 cm3 accounting towards the compactness of the samples with addition of PbO. Oxygen packing density increases from 30.996 to 32.637 whereas the oxygen molar volume is decreasing from 32.262 to 30.641 cm3 mol−1 with increase in PbO content. As PbO grows, E's modulus rises from 18.517 to 19.368 GPa, B's from 6.903 to 7.705 GPa, G's from 9.504 to 9.662 GPa, and L's from 19575 to 20.558 GPa. We used the Phy-X software to estimate the radiation shielding properties for the prepared glasses in a wide energy range of 0.015–15 MeV. We reported an enhancement in the mass attenuation coefficient (MAC) values when the PbO level increases from 70 to 77.5 mol %, this he highest MAC is found for PTC4, while the lowest MAC is reported for PTC1 sample. The photon energy has an impact on Linear attenuation coefficient (LAC) and the Greatest values of this parameter is reported at 0.015 MeV and equalling 501.64, 521.84, 549.53 and 569.17 cm−1 for the PTC1 to PTC4 glasses. In contrast, the lowest LAC is reported at 15 MeV (in the range of 0.283–0.313 cm−1). According to the LAC, the studied samples are able to attenuate more photons in the low energy region. The effective atomic number (Zeff) is also evaluated and similar to LAC, we found that the Zeff is increased due to the addition of PbO. From the results of different shielding factors, the inclusion of PbO alters the radiation attenuation performance.

Recycling of optical borosilicate waste glasses by Y2O3 doping for radiation shielding applications

In the present study, borosilicate glass-ceramics doped with Y2O3 were prepared and characterised for their structure and shielding prowess. Borosilicate waste glasses doped with Yttrium as a rare earth element from Y2O3 were prepared through the cold isostatic press method. The glass-ceramics had the chemical formula 81SiO2-12B2O3–4Na2O-3Al2O3-XY2O3, where X = 0, 10, 20% by weight. The structure of the prepared glasses was studied by the X-ray diffraction method while the density and hardness of the sample were measured experimentally. The ability of the glasses to absorb gamma-ray photons, moderate fast neutrons, and thermal neutrons was estimated from Monte Carlo simulations and established theoretical calculations. Samples containing 0% and 10% weight fraction exhibited mainly glassy structures, while the XRD spectrum of the sample containing 20% Y2O3 by weight displayed a glass-ceramics structure. The Vickers hardness values were calculated as 453, 501 and 551 HV under a 0.5 kg load for Y2O3 content of 0, 10, and 20 wt%. The density of the pristine borosilicate glass was 2.03 gcm−3. The addition of 10% and 20% by weight of Y2O3 increased the density by 9.85% and 18.07%, respectively. The mass attenuation coefficient values show strong energy fluctuations from 0.02046 to 5.18560 cm2/g for BS1, 0.02179–6.49902 cm2/g for BSY1, and 0.02313–7.81340 cm2/g as E decreases from 15 MeV to 15 keV. In addition, increasing the Y2O3 weight proportion in the samples increases photon buildup. The introduction of Y2O3 into the pristine borosilicate glass was found to increase the removal and total cross-sections for fast and moderated neutrons, respectively. The glass-ceramics demonstrated attributes useful for radiation absorption applications.

A study on gamma radiation shielding performance and characterization of graphitic carbon nitride

Graphitic Carbon Nitride (gCN) can be used in many fields such as sensing, solar energy and device construction. In this study, gCN obtained from urea and thiourea precursors were produced to determine the radiation shielding properties. The structural features and optical properties of these produced samples were investigated. Also, the radiation shielding properties were determined experimentally. Here, Linear Attenuation Coefficient values were determined experimentally and Mass Attenuation Coefficient, Half-Value Layer, Tenth-Value Layer and Mean Free Path values were calculated employing this value. According to obtained results, it is seen that obtained gCN can be used effectively in radiation shielding.

Physical Features of High-Density Barium–Tungstate–Phosphate (BTP) Glasses: Elastic Moduli, and Gamma Transmission Factors

We present elastic moduli, gamma radiation attenuation characteristics, and transmission factor of barium–tungstate–phosphate (BTP) glasses with the chemical formula (60-y)BaO-yWO3-40P2O5, where y = 10 (S1)–40 (S4) in steps of 10 mole%. Different types of mathematical and simulation approaches, such as the Makishima-Mackenzie model, the Monte Carlo method, and the online Phy-X/PSD software, are utilized in terms of determining these parameters. The total packing density (Vt) is enriched from 0.607 to 0.627, while the total energy dissociation (Gt) is enriched by increasing the WO3 content (from 52.2 (kJ/cm3). In the investigated glasses, increasing tungstate trioxide (WO3) contribution enhanced Young’s, shear, bulk, and longitudinal moduli. Moreover, Poisson’s ratio is improved by increasing the WO3 content in the BTP glasses. The 20BaO-40WO3-40P2O5 sample possessed the highest values of both linear (µ) and mass attenuation (µm) coefficients, i.e., (µ, µm)S4 > (µ, µm)S3 > (µ, µm)S2 > (µ, µm)S1. Moreover, the 20BaO-40WO3-40P2O5 sample had the lowest values of half (HVL) and tenth (TVL) layers, i.e., (half, tenth)S4 < (half, tenth)S3 < (half, tenth)S2 < (half, tenth)S1. The effective atomic number (Zeff) of the studied glasses has the same behavior as µ and µm. Finally, the 20BaO-40WO3-40P2O5 is reported with the minimum values of transmission factor (TF) for all the BTP investigated at a thickness of 3 cm. In conclusion, the sample with composition 20BaO-40WO3-40P2O5 which has the maximum WO3 reinforcement may be a beneficial glass sample, along with its advanced mechanical and gamma ray shielding properties.

Ionized and non-ionized radiation effects on coronary stent implantation

The purpose of this study is to examine the clinical radiation effects on patients with various stents. Several previous researches focused on the mechanical and physical features of the stents, but there have been few studies that focus on the interaction with radiological and clinical radiation. For stent material analysis, the ANSYS package program was employed. These materials and models are often built in three dimensions for three different types of stents made of three various materials. Estimates of blood pressure and thermal radiation were explored, as were the effects of non-ionizing radiation. Furthermore, the radiation attenuation characteristics of stent samples are investigated. The mass attenuation coefficient values are computed using MATLAB code over a large energy range of 0.015–15 MeV, and the findings are validated using theoretical WinXCom results. To determine the gamma-ray attenuation performances of the studied stent samples, variables such as the mass attenuation coefficient (MAC), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), effective atomic number (Zeff), exposure build-up factor (EBF), and energy absorption build-up factor (EABF) are computed. Effective removal cross-sections (ΣR) of stent samples were acquired to determine the capacity of stent samples to stop fast neutrons. Finally, the ability of stent samples to stop charged alpha and proton particles was evaluated utilizing mass stopping power and projected range parameters. The discovery demonstrates that S3 has the best attenuation as well as the best proton, alpha, and gamma radiation attenuation capability.

Nuclear radiation shielding performance of borosilicate glasses: Numerical simulations and theoretical analyses

The photon shielding performances of five different borosilicate-based glasses were investigated in this study using the FLUKA, GEANT4 and MATLAB codes, as well as the XCOM program, at photon energies ranging from 0.03 to 15 MeV. In this context, dependencies of the photon attenuation features with the variation of the photon energy and the chemical compositions have been carefully evaluated with Monte Carlo simulation and theoretical evaluation tools. The mass attenuation coefficient values and effective atomic numbers obtained for BaO-doped G5 glasses are found to be higher than those derived for G1-G4 samples. In other words, the Zeff results showed that high Z-elements such as Ba in a suitable amount should be inserted into the glass composition in order to improve the photon attenuation capability of the borosilicate glasses. The HVLs, TVLs, and MFPs of the studied borosilicate glasses are determined further, and the gamma shielding characteristics of the analyzed samples are found to be associated to the density of the glass, implying that high-density glass can be used for high-level attenuation performance. The exposure buildup factor (EBF) values have been further estimated via the G-P fitting approach. The results of such investigations, according to the work given, may be valuable in designing and fabricating new borosilicate-based glasses, which can then shield against potential radiation damage to environmental health.

Bismuth(III) oxide and boron(III) oxide substitution in bismuth-boro-zinc glasses: A focusing in nuclear radiation shielding properties

Doping the glass structure with Bi2O3 `is known to increase structural stability, and to drastically alter physical parameters including density and molar volume. The goal of this work was to assess the nuclear radiation attenuation competences of several types of glasses based on the xBi2O3-(70-x)B2O3-8BaO-16ZnO-5.5SiO2- 0.5Sb2O3 system. In order to determine the requisite gamma shielding parameters, as well as effective conductivity at 300 K and buildup factors, five different glasses with varied Bi2O3 concentration (i.e., from 10 mol.% to 30 mol.%) were examined thoroughly. These critical parameters were determined using the Phy-X/PSD program. In addition, factors such as half value layer (HVL), tenth value layer (TVL), and mean free path (mfp) were examined over a wide energy range of 0.015–15 MeV. The findings revealed that the amount of Bi2O3 reinforced in each sample is critical in determining the samples' shielding abilities. The linear attenuation coefficients (µ) and mass attenuation coefficient (µm) values were reported in the highest level for the sample with the highest Bi2O3 content. For glass sample A5, the lowest mean free path, half value layer, and tenth value layer values were also reported. The effective conductivity and effective atomic number had an inverse relationship with photon energy, meaning that as energy increased, the effective conductivity and effective atomic number declined fast, especially in low-energy regions. The greatest values for both parameters were found in glass sample A5. Furthermore, the exposure buildup factor and energy absorption buildup factor values for glass sample A5 were the lowest. A5 glass sample with the chemical composition 30Bi2O3-(70−30) B2O3-8BaO-16ZnO-5.5SiO2- 0.5Sb2O3 and a density of 5.8391 g/cm3 was found to have exceptional gamma-ray attenuation qualities, according to our findings. It can be concluded that the prospective attributes of Bi2O3-doped glass systems and associated glass compositions would be beneficial for scientific community in terms of providing a clearer view for some advanced applications of these glass types.

Fabrication of novel BaO–Al2O3–Bi2O3–B2O3 glass system: Comprehensive study on elastic, mechanical and shielding properties

The influence of barium oxide to the elastic and shielding properties of alumina bismuth borate glass system with the compositions (BaO)x(Al2O3)0.05 (Bi2O3)0.3 (B2O3)0.65-x where x = 0, 0.05, 0.10, 0.15, 0.20, 0.25, 0.30 mol% and classified as G1, G2, G3, G4, G5, G6 and G7 were investigated. The elastic properties of the glass system were examined by bulk density, molar volume, X-ray diffraction (XRD), Fourier transform infrared (FTIR) spectroscopy and non-destructive ultrasonic velocity measurement. The experimental results show that the density of the glass sample increase and molar volume of the glass sample was decrease. The XRD analysis revealed that the glass sample shows the characteristics of the amorphous nature without any sharp lines or peaks while the FTIR revealed the major broad absorption bands for borate glass structure. The ultrasonic velocities and elastic moduli measurement shows an increasing trend with the addition of BaO. The mass attenuation coefficient (MAC) demonstrated that the presence of BaO enhances the MAC values, resulting in an improvement in the shielding competency of the fabricated glasses. The highest interactions between photons and the atoms of the glasses occur around 0.122 MeV, and the glass samples have an excellent blocking capacity to photons, according to the effective atomic number (Zeff) data. Furthermore, the half value layer (HVL) revealed that when the BaO level in the composition increases, the HVL values will reduces. As a conclusion, the radiation shielding factors revealed that G7 glass with 30 mol% of BaO is the optimum performance of the produced samples.

The role of Bi2O3 on the gamma ray attenuation competence of lead-free silica borotellurite glasses between 0.284 and 1.275 MeV

The radiation shielding features of TeO2-B2O3-SiO2 glasses with varying amounts of Bi2O3 were studied at several energies emitted from three radioisotopes: Cs-137, Co-60, and Na-22. The addition of Bi2O3 increases the mass attenuation coefficient (MAC) of the glasses, and Glass 6; the glass with the greatest Bi2O3 content, has the highest MAC out of all the investigated samples. At low energies, 0.284 MeV, there is a great difference between the MAC values of the glasses which increase greatly from Glass 1 to Glass 6 but at 0.826 MeV, the MAC values still increase but very slowly which demonstrated that the MAC is greatly affected by the composition of the glasses at low energies. We investigated the relationship between the density of the glasses and their linear attenuation coefficients (LAC). We found that the LAC of the samples increases as density increases from 3.21 to 4.15 g/cm3, and Glass 6 has a better attenuation performance than Glasses 1–5. The ratio of the mean free paths (MFP) of Glass 1 and Glass 6 (MFPglass1/MFPGlass6) was reported. The highest MFPglass1/MFPGlass6 ratio is equal to 1.75 and occurs at 0.284. The average tenth value layer (TVL̅) of each glass was calculated at two energies; 0.284 MeV and 0.662 MeV, both of which are energies emitted from Cs-137. From the TVL̅results, increasing the Bi2O3 content of the glasses has a positive impact on the thickness of the glasses needed to attenuate the incoming radiation to safe levels.

Shielding properties and buildup factor of Al2O3/PbO-based ceramic materials

Gamma ray shielding properties have been assessed in terms of both linear and mass attenuation coefficient, half-thickness, and buildup factor using Al2O3/PbO-based ceramic material. These properties are influenced by the atomic number that is related to the density, as well as ionic bonds that are related to ceramic material. Al2O3 and PbO are promising gamma ray absorbing materials due to the ionic bond and high effective atomic number respectively, which attenuate gamma ray strongly. Due to the demand of applications and their requirements in industrial facilities and moving toward improving the performance of materials related to nuclear products in terms of design, manufacturing and low cost. This article presents interesting results of high values of mass attenuation coefficient of Al2O3/PbO groups in comparison to lead. Whereas, the interesting half-thickness values of these ceramic groups are relatively low. Furthermore, the buildup factor values are more than a unit of ceramic groups.

TeO2 for enhancing structural, mechanical, optical, gamma and neutron radiation shielding performance of bismuth borosilicate glasses

The synthesized 12Bi2O3– 8BaO–12ZnO-0.5CeO2-17.5SiO2- (50-x) B2O3- xTeO2 glasses with x = 0, 10, 20, 30 and 40 mol% (coded BiTe-0 to BiTe-40) were investigated in terms of physical, structural, optical and mechanical properties to examine the influence of CeO2 and TeO2 on the heavy metal oxide (HMO) borosilicate network. Density values increased continuously with increasing TeO2 concentration with BiTe-40 glass exhibiting maximum value of 5.0875 gcm−3. This property helped in enhancement of refractive index values from 1.769 for BiTe-0 to 1.942 for BiTe-40. Fourier transform infrared (FTIR) analysis of studied glasses revealed the presence of additional small peak at 683 cm−1 in BiTe-30 and BiTe-40 which confirmed the formation of stable TeO4 units in the glass network. The deep brown colour of the glass existing due to bismuth's presence was nullified by CeO2 and TeO2 additives which improved transparency of the glass. Urbach analysis of these glasses led to optical bandgap variation between 3.27 eV and 2.73 eV for 0–40 mol% TeO2 concentration. Makishima and Mackenzie model was utilized for evaluation of elastic property of the glasses, and Poisson's ratio ranging between 1.935 and 1.953 was obtained. Vickers micro-indentation test on the current glasses revealed decreasing microhardness from 4.116 to 4.076 GPa with TeO2 variation from 0 to 40 mol% at 9.8 N load. Gamma radiation shielding parameters were determined using Phy-X/PSD software and it was found that BiTe-40 glass produce maximum MAC (mass attenuation co-efficient) values in high photon energy region 3.5–15 MeV. The present article also contains a detailed emphasis on behaviour of gamma radiation build-up factors at different incident photon energy and TeO2 concentration. The increasing trend of exposure build up factor (EBF) was seen with increasing penetration depth inside the samples at all energies, indicating that glasses of larger thickness improve the escape probability of photons. Meanwhile, fast neutron removal cross-section (FNRCS) was highest for BiTe-10 sample (0.10118 cm−1) which also surpassed the value of ordinary concrete (0.093 cm−1). Overall, the present glass system bested other conventional shields available commercially in terms of gamma and neutron radiation shielding effectiveness.

Numerical Investigation on Photon Sensing Parameters for Some Thermoluminescence Dosimeters: A Comparative Study

In the present work, twelve inorganic thermoluminescence dosimeteric (TLD) materials doped with some rare earth elements (LiF:Sm, LiBaP2O7:Eu, CaCO3:Eu, CaSO4:Dy, SrSO4:Sm, CdSO4:Dy, BaSO4:Eu, Li2B4O7:Dy, MgB4O7:Gd, Al2O3:Gd, MgAl2O4:Ce and LiCaAlF6:Eu) and three organic TLD materials (C3H7NO2, C7H8O2 and C4H6BaO4) were selected for comparative analysis on the basis of different photon sensing parameters. About nine photon sensing parameters viz. mass attenuation coefficient (MAC), linear attenuation coefficient (LAC), mean free path (mfp), half value layer (HVL), tenth value layer (TVL), effective atomic number (EAN), effective electron number (EEN), exposure buildup factor (EBF) and energy absorption buildup factor (EABF) were obtained for the selected fifteen TLDs. The simultaneous variation of these photon sensing parameters for the selected TLDs with photon energy and composition has been analyzed. The results of present comparative analysis help radiation physicists to easily select a particular dosimeter for their research laboratory from different existing compositions. All photon sensing parameters viz. MAC, LAC, mfp, HVL, TVL, EAN, EEN, EBF and EABF for selected TLDs strongly depend upon incident energy and chemical composition in lower and higher energy regions. Among the selected TLDs; BaSO4: Eu3+ offers best results (maximum values for MAC, EAN, EEN; and minimum values for mfp, HVL, TVL, EBF, EABF); whereas MgB4O7:Gd3+ offers EAN value close to tissue and less variation in most of the sensing parameters with respect to photon energy.

Experimental shielding properties for a novel glassy system

In the current study, we fabricated a series of boro-tellurite glass samples with a composition 10SrO–10Al2O3–10MoO3-(70-x)B2O3-xTeO2, where (x = 0, 17.5, 35, 52.5, and 70 mol%) via an ordinary melt-quench method. The glass structure was explored by X-ray diffraction (XRD), physical and structural properties. XRD results affirm the existence of two broad peaks, proving the amorphous state of the current glasses. The acquired results exhibit a linear relationship between the density, Poisson's ratio, and the addition of TeO2 amounts. The addition of TeO2 to the glass system shows a rise in glass stability and a reduction in packing density. Additionally, the values of mass attenuation coefficient (MAC) were determined experimentally within five energies (0.184, 0.280, 0.661, 0.710, and 0.810 MeV) from two radiation sources (166Ho and 137Cs). The (MAC)exp results were compared with XCOM values, and the compared values showed excellent compatibility. From the experimental results, many radiation shielding features involving half-value layer (HVL), mean free path (MFP), tenth value layer (TVL), and radiation protection efficiency (RPE) were computed. From the obtained results, it can be concluded that the TeSB4 sample has the highest stability and absorption for radiation, indicating the ability to use it as a radiation shielding substance.

Investigating the effect of gamma-ray interaction on the stability and physicochemical properties of turmeric and ginger using Monte Carlo simulation

Turmeric and ginger are among the most widely used medicinal plants due to their health benefits and bioactivities, which include antiviral and antioxidant properties. However, these plants are usually irradiated to increase their shelf life and quality. Using a Monte Carlo simulation, this study investigates the structural changes in the active ingredients of ginger and turmeric after irradiation. The Linear Attenuation Coefficient (LAC) and Mass Attenuation Coefficient (MAC) calculations are interrelated with the properties of materials in terms of low and high radiation absorption. According to the results, curcumin showed better absorption attributes compared to 6-gingerol. The results also indicated an increase in the total antioxidant activity and b value (yellowness) of turmeric after treatment with 5 kGy irradiation. On the other hand, positive correlations were also found between MAC and ABTS values. It can be concluded that irradiation up to 5 kGy dosages could be beneficial for turmeric as it both prevents microbial contamination and increases its antioxidant activity. However, the results indicated that the effect of irradiation on the antioxidant activity varies depending on the nature of the product, thus further studies are required to better understand the effect of irradiation on the bioactive components of food materials.