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In this study, three different ilmenite-limonite (ILC) concretes were modeled in terms of determining the effect of filler type and filler size on the enhancement of radiation shielding properties in the 0.142-1.33 MeV gamma-ray energy range. Accordingly, ILC concrete, micro (50 mu m) and nano (50 nm) WO3, and micro (50 mu m) and nano (50 nm) PbO filler added ILC samples were modeled. MCNPX simulations of micro- and nano-sized particles inside of the ILC sample were performed using lattice (LAT) and universe (U) features of MCNPX (version 2.7.0) code. The greatest increase in mass attenuation coefficient was reported from micro-PbO to nano-PbO filler as 7.88% at 0.142 MeV energy value. The study's findings indicated that decreasing the particle size of the additive material decreases the mean free path and so increases the quantity of gamma radiation interacting per unit distance. Although we validated the consistency of our input against the standard NIST database, several points, such as experimental investigations of nanoparticles in ILC concrete, nanoparticle distributions, and the effect of this distribution on overall shielding enhancement, should be investigated further. WOS:000889376700001 Q3

We present the findings of an extensive examination on newly designed CdO-rich and transparent glass shields for nuclear medicine facilities in lieu of traditional and unfavorable materials, such as lead and concrete. Gamma-ray transmission factors of newly designed glass shields are determined using a variety of diagnostic, therapeutic, and research radioisotopes, including 67Ga, 57Co, 111In, 201Tl, 99mTc, 51Cr, 131I, 58Co, 137Cs, 133Ba, and 60Co. A general-purpose Monte Carlo code MCNPX (version 2.7.0) is used to determine the attenuation parameters of different material thicknesses. Next, the findings are compared using a standard concrete shielding material. The results indicate that adding more CdO to the glass composition improves the overall gamma-ray attenuation properties. As a result, among the heavy and transparent glasses developed, the C40 sample containing 40% CdO exhibited the best gamma-ray absorption properties against all radioisotopes. Furthermore, the gamma-ray absorption characteristics of this created high-density glass were shown to be better to those of a standard and heavy concrete sample. It can be concluded that the newly developed CdO-rich and transparent glass sample may be used in medical radiation fields where the radioisotopes examined are used in daily clinical and research applications.

We present the optical, physical, and alpha/proton absorption properties of C-type P2O5–TeO2–ZnO ternary glass structures with a nominal composition of 20P2O5.30TeO2. (50-x)ZnO.xCdO (x = 15, 20, 30, 40 mol%). Using experimental methods, the physical and optical features of manufactured glasses are measured. The densities of the produced samples are increased due to ZnO/CdO translocation. Sixteen different bands are obtained as a result of deconvolution process. The C20 sample is reported with the largest optical band gap (3.530 eV) while the C15 sample is reported with the lowest (3.450 eV). According to our results, keeping the CdO concentration of ternary glasses around 40% is crucial for maintaining the glassy structure since glassy structure is distorted when %50 CdO (i.e., C50 sample) is incorporated into the glass structure. The shortest distances that alpha and protons may travel at the same energy levels are found in the C40 sample, which has the largest CdO contribution and the highest glass density. Due to the C40 sample’s greatest resistance to the movement of heavy particles within the material, this is the case. Our results have shown that 40% CdO contribution improves absorption of alpha and protons within the absorber material. Due to their great transparency and promising material features, it can be concluded that ternary glasses containing CdO might serve as excellent glass shields. WOS:000854502000004 Q2 - Q3

The current contribution goal is to measure the distribution of the radionuclide within the exposed rock units of southwestern Sinai, Seih-Sidri area, and assess the radiological risk. Gneisses, older granites, younger gabbro, younger granites, and post granitic dikes (pegmatites) are the main rock units copout in the target area. Radioactivity, as well as radiological implications, were investigated for forty-three samples from gneisses (seven hornblende biotite gneiss and seven biotite gneiss), older granites (fourteen samples), and younger granites (fifteen samples of syenogranites) using NaI (Tl) scintillation detector. External and internal hazard index (Hex, Hin), internal and external level indices (Iα, Iγ), absorbed dose rates in the air (D), the annual effective dose equivalent (AED), radium equivalent activity (Raeq), annual gonadal dose (AGDE), excess lifetime cancer risk (ELCR), and the value of Upper Continental Core 232Th/238U mass fractions were determined from the obtained values of 238U, 232Th and 40K for the examined rocks of Seih-Sidri area. The average 238U mg/kg in hornblende biotite gneiss and biotite gneiss, older granites, and syenogranites is 2.3, 2.1, 2.7, and 8.4 mg/kg, respectively, reflecting a relatively higher concentration of uranium content in syenogranites. The results suggest that using these materials may pose risks to one’s radiological health. © 2022 by the authors. PNURSP2022R173; Universitatea 'Dunărea de Jos' Galați, UDJG Conceptualization, M.S.K.; data curation, M.S.K., E.S.R.L., A.E., H.A.A. and H.M.H.Z.; formal analysis, M.S.K., E.S.R.L., A.E., H.A.A. and H.M.H.Z.; funding acquisition, A.E., G.A.A. and H.M.H.Z.; investigation, M.S.K., E.S.R.L., A.E., H.A.A. and H.M.H.Z.; methodology, M.S.K., E.S.R.L., A.E., M.A.M.U., H.A.A., S.A.M.I. and H.M.H.Z.; project administration, A.E. and H.M.H.Z.; resources, M.S.K., E.S.R.L. and H.M.H.Z.; software, A.E. and H.M.H.Z.; supervision, A.E. and H.M.H.Z.; validation, G.A.A., M.S.K., E.S.R.L., M.A.M.U., H.A.A., S.A.M.I. and H.M.H.Z.; visualization, H.M.H.Z.; writing—original draft, M.S.K., E.S.R.L., A.E., H.A.A. and H.M.H.Z.; writing—review and editing, G.A.A., M.S.K., E.S.R.L., A.E., M.A.M.U., S.A.M.I., H.A.A. and H.M.H.Z. The researcher H.A.A. is funded by a scholarship under the Joint (Executive Program between Egypt and Russia). All authors have read and agreed to the published version of the manuscript.

Solar cells in superstrate arrangement need a protective cover glass as one of its main components. The effectiveness of these cells is determined by the cover glass’s low weight, radiation resistance, optical clarity, and structural integrity. Damage to the cell covers brought on by exposure to UV irradiation and energetic radiation is thought to be the root cause of the ongoing issue of a reduction in the amount of electricity that can be generated by solar panels installed on spacecraft. Lead-free glasses made of xBi2O3–(40 − x)CaO-60P2O5 (x = 5, 10, 15, 20, 25, and 30 mol%) were created using the usual approach of melting at a high temperature. The amorphous nature of the glass samples was confirmed using X-ray diffraction. At energies of 81, 238, 356, 662, 911, 1173, 1332, and 2614 keV, the impact of various chemical compositions on gamma shielding in a phospho-bismuth glass structure was measured. The evaluation of gamma shielding revealed that the results of the mass attenuation coefficient of glasses increase as the Bi2O3 content increases but decrease as the photon energy increases. As a result of the study conducted on the radiation-deflecting properties of ternary glass, a lead-free low-melting phosphate glass that exhibited outstanding overall performance was developed, and the optimal composition of a glass sample was identified. The 60P2O5–30Bi2O3–10CaO glass combination is a viable option for use in radiation shielding that does not include lead.

The nuclear spectroscopy method has long been used for advanced studies on nuclear physics. In order to decrease costs and increase the efficiency of nuclear radiation investigations, quick and efficient solutions are required. The purpose of this research was to calculate the whole energy peak efficiency values for a range of gamma-ray energies, from 30.973 keV to 1408 keV, at various source-detector distances using the MCNPX Monte Carlo code, which is extensively used in nuclear medicine, industry, and scientific research. As a result, the modeled detectors' full-energy peak efficiencies were calculated and compared to both experimental data and Monte Carlo simulations. Experiment results and prior studies using Monte Carlo simulations were found to be very consistent with these results. The counting efficiency against source-detector distance is then calculated using the modeled detectors. The data we have show that LaBr

The direct effects of tungsten trioxide (WO3) on gamma radiation attenuation properties of tungsten/barium/phosphate glasses with chemical form xWO3–(50-x/2)BaO–(50-x/2)P2O3, x = 0 (S1)–60 (S7) in steps of 10 mol% has been investigated. To this end, Phy-X/PSD software and Monte Carlo code were applied. The increased amount of WO3 in the glass composition, on the other hand, contributed positively to the increase in density and radiation sensing properties. At the lowest and highest WO3 contributions, a nearly twofold increase in HVL value was seen for the S1 and S7 glass samples, respectively, with S7 having the lowest HVL values. The HVL has obeyed the trend as: (HVL)S1 > (HVL)S2 > (HVL)S3 > (HVL)S4 > (HVL)S5 > (HVL)S6 > (HVL)S7. The variation of the tenth value layer (TVL) for all studied glasses has the same trend of HVL. In terms of mean free path (MFP), there was negative effect of WO3 concentration on the trend of MFP. Consequently, S7 glass sample has the lowest values of MFP, while the S1 glass sample has the highest values. Therefore, (MFP)S1 > (MFP)S2 > (MFP)S3 > (MFP)S4 > (MFP)S5 > (MFP)S6 > (MFP)S7. A comparison of the HVL of S7 glass sample with some commercial radiation shielding materials such as different types of concrete and RS-253-G18 glasses has been performed and concluded that the S7 glass sample is superior as radiation shielding material than several commercial materials. It can be concluded that WO3 reinforcement serves a multipurpose of increasing the density and hence the gamma-ray-shielding characteristics of comparable glass compositions. © 2022, The Author(s), under exclusive licence to Springer-Verlag GmbH, DE part of Springer Nature. 2-s2.0-85129716802

In this study, three different sliding bearing alloy samples were investigated in terms of their performance on attenuation characteristics and behavioral attitudes under 0.015–15 MeV gamma-ray exposure. Accordingly, different types of advanced calculation methods were utilized to calculate the radiation shielding parameters. Next, several gamma-ray shielding parameters and exposure rates in addition to fast neutron removal cross-section were determined. Furthermore, exposure and energy absorption buildup factors were determined by using G-P fitting method. Mass attenuation coefficients (MAC) values were recorded as 2.5246, 2.5703, and 2.5827 (cm2 /g) for Alloy1, Alloy2, and Alloy3 samples at 15 MeV photon energy, respectively. At 40 mfp, the highest EBF values were reported as 1,376,274, 1,003,593, and 969,373 for Alloy1, Alloy2, and Alloy3 samples. The results of this extended investigation showed that the Alloy3 sample with the highest Pb reinforcement amount has superior shielding capability among the investigated samples. It can be concluded from the results that substitution of Pb with Bi in the recent alloy structure has a monotonic effect on different types of shielding parameters. Therefore, it can also be concluded that Pb is a remarkable tool for the improvement of the shielding properties of studied alloy structures. © 2022 by the authors. Licensee MDPI, Basel, Switzerland. Deanship of Scientific Research, King Faisal University, DSR, KFU: R.G.P.1/1/42 Funding: The authors extend their appreciation to the Deanship of Scientific Research at King Khalid University for funding this work through research groups program under grant number R.G.P.1/1/42.

In this study, glass samples of composition 20PbO-20CaO-20Sand-(40 − x)B2O3-xCeO2, where x = 0, 2.5, 5, 7.5, and 10 in wt.% and sand = SiO2 (90.4%) + CaO (2.8%) + ZrO2 (2.3%) + Fe2O3 (2.1%), were fabricated via the ordinary melt quenching technique. The thermal and optical properties of the glasses were experimentally investigated using differential scanning calorimetry (DSC) analysis, which is measured as a function of temperature based on the difference in the amount of heat needed to raise the temperature of a sample and reference. All glasses were found to be thermally stable up to 550°C. The glass transition temperature (Tg) varied from 211°C to 219°C, crystallization temperature (Tc) varied from 303°C to 310°C, and melting point (Tm) was 577°C. The values of the indirect optical energy band gaps (EOptical, Indirect) reduced from 2.63 eV to 2.28 eV, while the direct gaps (EOptical, Direct) reduced from 5.07 eV to 4.17 eV. Urbach’s energy (EU) was changed from 0.42 eV to 0.46 eV. The dielectric constant behaved similarly to the refractive index and absorption coefficient of the proposed glasses. The refractive index data were analyzed to obtain important optical information and the corresponding derivative electrical parameters, namely, the oscillator energy, dispersion energy, dielectric constant at high frequency, the dielectric loss, and the energy-loss functions. There was a remarkable increase in the optical conductivity (σopt) with increasing CeO2 content, with peaks appearing in all samples doped by CeO2 and reaching a peak maxima of about 2.72–3.10 eV. Volume energy loss (VELF) and surface energy loss (SELF) functions were increased with increasing CeO2 content, with a characteristic peak at around 3.47 eV for all proposed samples. © 2022, The Minerals, Metals & Materials Society. 2-s2.0-85124492830 WOS:000754140900005 Q3

The specific activity of U-238 and Th-232, as well as K-40 radionuclides, in twenty-nine investigated medicinal herbs used in Egypt has been measured using a high-purity germanium (HP Ge) detector. The measured values ranged from the BDL to 20.71 ± 1.52 with a mean of 7.25 ± 0.54 (Bq kg−1) for uranium-238, from the BDL to 29.35 ± 1.33 with a mean of 7.78 ± 0.633 (Bq kg−1) for thorium-232, and from 172 ± 5.85 to 1181.2 ± 25.5 with a mean of 471.4 ± 11.33 (Bq kg−1) for potassium-40. Individual herbs with the highest activity levels were found to be 20.71 ± 1.52 (Bq kg−1) for uranium-238 (H4, Thyme herb), 29.35 ± 1.33 (Bq kg−1) for thorium-232 (H20, Cinnamon), and 1181.2 ± 25.5 (Bq kg−1) for potassium-40 (H24, Worm-wood). (AACED) Ingestion-related effective doses over the course of a year of uranium-238 and thorium-232, as well as potassium-40 estimated from measured activity concentrations, are 0.002304 ± 0.00009 (minimum), 0.50869 ± 0.0002 (maximum), and 0.0373 ± 0.0004 (average)(mSv/yr). Radium equivalent activity (Raeq), annual gonadal dose equivalent (AGDE), absorbed gamma dose rate (Doutdoor, Dindoor), gamma representative level index (I), annual effective dose (AEDtotal), external and internal hazard index (Hex, Hin), and excess lifetime cancer risk were determined in medicinal plants (ELCR). The radiological hazards assessment revealed that the investigated plant species have natural radioactivity levels that are well within the internationally recommended limit. This is the first time that the natural radioactivity of therapeutic plants has been measured in Egypt. In addition, no artificial radionuclide (for example, 137Cs) was discovered in any of the samples. Therefore, the current findings are intended to serve as the foundation for establishing a standard safety and guideline for using these therapeutic plants in Egypt. © 2022 by the authors. Licensee MDPI, Basel, Switzerland. PNURSP2022R173 This work was funded by Princess Nourah bint, Abdulrahman University, Research Supporting Project number (PNURSP2022R173) Princess Nourah bint, Abdulrahman University, Riyadh, Saudi Arabia.

Thallium-activated sodium iodide (NaI(Tl)) detectors can be used in gamma cameras, environmental radiation assessments, including radiation emission levels from nuclear reactors, and radiation analysis equipment. This three-phase investigation aimed to model a standard NaI(Tl) detector using the Monte Carlo N-Particle eXtended (MCNPX) general-purpose Monte Carlo simulation techniques. Accordingly, a standard NaI(Tl) detector was designed along with the required properties. Next a validation study of the modelled NaI(Tl) detector has been performed based on the experimental results for absolute detector efficiency values obtained from 226Ra, 232Th, and 40K radioisotopes. Our findings indicate that the obtained absolute detector efficiency values are quite close to used experimental values. Finally, we used the modelled detector for determination of mass attenuation coefficients of Ordinary concrete, Lead, Hematite-serpentine concrete, and Steel-scrap concrete at 186.1, 295.22, 351.93, 609.31, 1120.29, 1764.49, 238.63, 911.2, 2614, and 1460.83 keV gamma-ray energies. Additionally, according to our findings, mass attenuation coefficients obtained from the newly designed detector are compatible with the standard NIST (XCOM) data. To conclude, continuous optimisation procedures are strongly suggested for sophisticated Monte Carlo simulations in order to maintain a high degree of simulation reliability. As a result, it can be concluded that the validation of the simulation model is necessary using measured data. Finally, it can also be concluded that the validated detector models are effective instruments for obtaining basic gamma-ray shielding parameters such as mass attenuation coefficients.

High-density glasses of neodymio-cadmium lead borate of chemical composition xNd2O3/20CdO/20PbO/(57-x)B2O3/3Na2O, where (0 (0Nd) ≤ x ≤ 5 (5Nd) wt%) have been fabricated by a melt quenching process. Physical, structure properties as well as gamma-radiation and neutron shielding effectiveness in wide photon energy range 0.015–15 MeV have been examined. The amorphous nature of xNd-glasses was confirmed, where there was a lack of their crystallinity. Density was gradually increased from 5.006 g/cm3 for 0Nd-glass sample to 5.245 g/cm3 for 5Nd-glass sample. In terms of the mass attenuation coefficient (MAC), introducing Nd3+ ions in the glass matrix has a direct constructive influence on the obtained values of MAC. Generally, the MAC trend follows the order (MAC)5Nd > (MAC)4Nd > (MAC)3Nd > (MAC)2Nd > (MAC)1Nd > (MAC)0Nd. The linear attenuation coefficient (LAC) has a similar trend as MAC for all xNd-glasses. In terms of the half-value layer (T1/2), the 5Nd-glasses possessed the minimum T1/2 values (0.004 cm at 15 keV to 4.301 cm at 15 MeV). Therefore, the T1/2 of the fabricated xNd-glasses has an inverse behavior of the MAC and LAC. Thus, (T1/2)0Nd > (T1/2)1Nd > (T1/2)2Nd > (T1/2)3Nd > (T1/2)4Nd > (T1/2)5Nd. The effective atomic number (Zeff) parameter follows the order (Zeff)5Nd > (Zeff)4Nd > (Zeff)3Nd > (Zeff)2Nd > (Zeff)1Nd > (Zeff)0Nd. In the energies preferred for radiation applications, 5Nd-glasses possess very low exposure (EBF) and energy absorption (EABF) buildup factor values. The fast neutron removal cross-section (FNRC) of the fabricated glasses is improved as the Nd3+ content increases in the glass matrix. © 2022, The Author(s), under exclusive licence to Springer-Verlag GmbH, DE part of Springer Nature. Taif University, TU Taif University Researchers Supporting Project number (TURSP-2020/84), Taif University, Taif, Saudi Arabia.

Gadolinium (III)-containing (1, 3 and 5 wt.%) silicate-based bioactive glass powders were synthesized by sol–gel method and subsequently die pressed to fabricate disc-shape glass samples. Sintering was performed at 690 °C for 1 h in air atmosphere. Physical, structural, and mechanical properties (compressive strength and Vickers hardness) of the fabricated glass pellets were investigated. Results showed that prepared glass samples were amorphous after sintering and any detrimental effect of Gd2O3 was not observed on the densification. An increase in bulk density and in compressive strength was obtained as the gadolinium (III) concentration was increased. On the other hand, a significant influence of the rare-earth element on the Vickers hardness was not seen. For the sample containing gadolinium (III) at highest concentration, Vickers hardness was measured to be 3.25 ± 0.23 GPa. Our findings indicate that increasing the quantity of Gadolinium (III) significantly affects the gamma-ray attenuation qualities of bioactive glass samples. The addition of Gadolinium (III) improved the attenuation qualities of the bioactive glass samples across a broad energy range. As a result, it can be concluded that Gadolinium (III) and its monotonic effect may be used to modify the basic features of bioactive glass samples. In addition, it can be concluded that this monotonic effect may be employed to optimize the circumstances of use of associated bioactive materials based on their requirements in medical and engineering applications. © 2022, The Author(s), under exclusive licence to Springer-Verlag GmbH, DE part of Springer Nature.

This study aimed to investigate the nuclear radiation shielding properties of erbium (Er)-reinforced and samarium (Sm)-reinforced borate glasses. In the 0.015–15 MeV photon energy range, attenuation coefficients, as well as half-value layer tenth-value layers, and the mean-free path have been calculated. Additionally, effective, and equivalent atomic numbers, effective atomic weight, electron density, and exposure and energy absorption build-up factors were also calculated. To evaluate the overall nuclear radiation attenuation competencies of Er-rich and Sm-rich glasses, effective removal cross-section values for fast neutrons and projected range/mass stopping power values for alpha and proton particles were also determined. The glass sample BZBEr2.0 had the highest linear and mass attenuation coefficients (µ and µ m), effective conductivity (C eff), the effective number of electrons (N eff), and effective atomic number (Z eff) values as well as the lowest half-value layer (T 1/2), tenth value layers (T 1/10), mean free path (λ), exposure build-up factor, and energy absorption build-up factor values. µ m values were reported as 2.337, 2.556, 2.770, 2.976, 2.108, 2.266, 2.421, 2.569, and 2.714 for BZBEr0.5, BZBEr1.0, BZBEr1.5, BZBEr2.0, BZBSm0.0, BZBSm0.5, BZBSm1.0, BZBSm1.5, and BZBSm2.0 glass samples at 0.06 MeV, respectively. The results showed that Er has a greater effect than Sm regarding the gamma-ray shielding properties of borate glasses. The results of this investigation could be used in further investigations and added to older investigations with the same aim, to aid the scientific community in determining the most appropriate rare-earth additive, to provide adequate shielding properties based on the requirement.

Mechanical properties, elastic moduli, transmission factors (TFs), and gamma-ray shielding performance of quaternary glass systems with chemical composition (0.25−x)Bi2O3–xB2O3−0.75(50%P2O5−50%V2O5), where x = 0.05 (S1), 0.10 (S2), 0.15 (S3), and 0.20 (S4) mol%, were comprehensively studied. The MCNPX code, Phy-X/PSD software, and the Makishima–Mackenzie model were utilized to achieve the mentioned purposes. The values of the packing density (V t) decreased from 0.634432 to 0.600611, while those of the dissociation energy (G t) increased from 51.6125 kJ/cm3 for the S1 glass sample (with Bi2O3 = 5 mol%) to 56.7525 kJ/cm3 for the S4 glass sample (with Bi2O3 = 20 mol%). This means that the mechanical properties were enhanced by increasing the Bi2O3 content in glasses. Linear (µ) and mass attenuation (µ m) coefficients for the S4 glass sample were the greatest compared to those for glass materials investigated, i.e., (µ, µ m)S1 < (µ, µ m)S2 < (µ, µ m)S3 < (µ, µ m)S4. Half- and tenth-value layers (HVL and TVL, respectively) follow the trend: (HVL, TVL)S1 > (HVL, TVL)S2 > (HVL, TVL)S3 > (HVL, TVL)S4. The effective atomic number (Z eff) of investigated glasses has the same trend as of linear and mass attenuation coefficients. Our findings indicate that increasing the amount of Bi2O3 reinforcement decreased the exposure buildup factor and energy absorption buildup factor values for all mean free path values (0.5–40 mfp). All glasses recorded the minimum TF values at a thickness of 3 cm. The findings would benefit the scientific community in determining the most appropriate additive bismuth(iii) oxide/diboron trioxide type and related glass composition to provide the shielding properties previously mentioned in terms of needs and utilization requirements, as well as the most suitable glass composition.

Through experimental and modeling techniques, this research sought to investigate the reflections of partial replacement of CaO–SiO2 with Tungsten(III) oxide and its effect on structural, optical, and physical properties. The melt quenching technique was used to produce several glass samples with a nominal composition of 5Na2O–10Al2O3–(42.5 − x)SiO2–(42.5 − x)CaO–xWO3 system (where x = 0, 0.2, 0.4, and 0.6 wt.&). The amorphous structure of calcium-silicon glasses was determined experimentally using the XRD technique. UV and density studies were also performed to determine optical and material properties. To determine the effect of this replacement on nuclear radiation shielding improvement, the linear attenuation coefficient was computed across a broad energy range of 0.015–15 MeV using narrow beam geometry and the simulated gamma-ray transmission technique. The radiation parameters were simulated using sophisticated Monte Carlo simulations using the FLUKA general-purpose radiation transport algorithm and compared using the NIST XCOm theoretical computation. To maximize the substitution's synergistic impact, the present investigation's findings were correlated with each other for the purpose of determining availability for nuclear shielding purposes. It was discovered that when the WO3 content rises from 0 to 20% wt— percent, both direct and indirect bandgaps reduce, resulting in increased transparency. In addition, the Urbach energy (Eu) yields a rise in proportion to the amount of doping elements in the samples. On the other hand, gamma-ray attenuation measurements revealed that shielding parameters are directly proportional to the WO3-wt percent concentration; furthermore, the addition of WO3 substantially enhances the shielding capacity of the investigated glasses against gamma radiation. It is observed that when additional WO3 is added, both the real and imaginary components of the dielectric constant increase. The most effective shield was determined to be the NSCW20 sample. As a result, a WO3-calcium-silicon glass containing 20% WO3 was selected as the optimum radiation filter. © 2022, The Author(s), under exclusive licence to Springer-Verlag GmbH, DE part of Springer Nature. 2-s2.0-85125278487

Gamma-ray shielding properties of eight different metallic glasses based on CuxZr100-x: x = 35 (Cu35Zr65) − 70 (Cu70Zr30) were determined using Monte Carlo simulations and Phy-X/PSD software. A typical gamma-ray transmission setup has been modeled in MCNPX Monte Carlo code. The general trend of the linear attenuation coefficients (μ) was reported as (μ)Cu35Zr65 < (μ)Cu40Zr60 < (μ)Cu45Zr55 < (μ)Cu50Zr50 < (μ)Cu55Zr45 < (μ)Cu60Zr40 < (μ)Cu65Zr35 < (μ)Cu70Zr30. In terms of half value layer (HVL) values, the Cu35Zr65 sample has the highest value (2.984 cm) and the Cu70Zr30 sample has the lowest value (2.769 cm) at 8 MeV photon energy. The mean free path (MFP) values were 4.305 and 3.995 cm for Cu35Zr65 and Cu70Zr30 samples, respectively. Generally, MFP and HVL values of the studied glasses were reported as (MFP,HVL)Cu35Zr65 > (MFP,HVL)Cu40Zr60 > (MFP,HVL)Cu45Zr55 > (MFP,HVL)Cu50Zr50 > (MFP,HVL)Cu55Zr45 > (MFP,HVL)Cu60Zr40 > (MFP,HVL)Cu65Zr35 > (MFP,HVL)Cu70Zr30 for all photon energy range. The Cu70Zr30 sample showed maximum values of both the effective conductivity (C eff) and effective electron density (N eff). In addition, the Cu70Zr30 sample has minimum exposure and energy absorption buildup factor (EBF and EABF) values at all studied gamma-ray energies. The results revealed that the Cu70Zr30 sample has superior attenuation properties among all studied samples.

In this study, physical, chemical, structural and radiation attenuation properties of some granite samples collected from Kütahya-Simav and İzmir (Bergama and Karaburun) were investigated. The true particle density of the studied granite samples was in the range of 2.65 g cm−3 to 2.72 g cm−3 and the median particle diameter was between ∼12 μm and 41 μm. According to the structural examination results obtained from the study, the chemical compositions of the extracted granite samples varied by area. While SiO2 was the dominating component in certain locations, it was replaced by Fe2O3 in another. This condition also had a direct effect on the densities of the granite samples extracted. At the conclusion of the study, it was found that the predominant factor affecting the radiation shielding characteristics of granites was the quantity of Fe2O3 in the composition, with the greatest gamma-ray shielding qualities supplied by samples 4 and 5, which had the highest Fe2O3 ratio. Our results indicate that sample 5 and the previously studied Capao Bonita sample had comparable half value layer values at low, medium, and high gamma ray levels. It may be concluded that Izmir granites are a more attractive option to granite for usage as radiation shielding building materials, owing to their high Fe2O3 concentration, and may be a feasible alternative to less desirable concrete materials for shielding applications.

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.

In this study, a group of heavy metal oxide glasses with a nominal composition of 55B2O3 + 19.5TeO2 + 10K2O + (15−x) PbO + xAl2O3 + 0.5Eu2O3 (where x = 0, 2.5, 5, 7.5, 10, 12.5, and 15 in wt.%) were investigated in terms of their nuclear radiation shielding properties. These glasses containing lanthanide-doped heavy metal oxide were envisioned to yield valuable results in respect to radiation shielding, and thus a detailed investigation was carried out; the obtained results were compared with traditional and new generation shields. Advanced simulation and theoretical methods have been utilized in a wide range of energy regions. Our results showed that the AL0.0 sample with the highest PbO contribution had superior shielding properties in the entire energy range. The effective removal of cross-sections for fast neutrons (ΣR) was also examined. The results indicated that AL5.0 had the greatest value. While increasing the concentration of Al2O3 in samples had a negative effect on the radiation shielding characteristics, it can be concluded that using PbO in the Eu3+ doped heavy metal oxide glasses could be a useful tool to keep gamma-ray shielding properties at a maximum level.

The radiation shielding characteristics of samples from two TeO2 and Sb2O3-based basic glass groups were investigated in this research. TeO2 and Sb2O3-based glasses were determined in the research as six samples with a composition of 10WO3-(x)MoO3-(90 − x)(TeO2/Sb2O3) (x = 10, 20, 30). A general purpose MCNPX Monte Carlo code and Phy-X/PSD platform were used to estimate the radiation shielding characteristics. Accordingly, the linear and mass attenuation coefficients, half value layer, mean free path, variation of the effective atomic number with photon energy, exposure and built-up energy factors, and effective removal cross-section values were determined. It was determined that the results that were produced using the two different techniques were consistent. Based on the collected data, the most remarkable findings were found to be associated with the sample classified as T80 (10WO3 + 10MoO3 + 80TeO2). The current study showed that material density was as equally important as composition in modifying radiation shielding characteristics. With the T80 sample with the greatest density (5.61 g/cm3) achieving the best results. Additionally, the acquired findings were compared to the radiation shielding characteristics of various glass and concrete materials. Increasing the quantity of MoO3 additive, a known heavy metal oxide, in these TeO2 and Sb2O3-based glasses may have a detrimental impact on the change in radiation shielding characteristics.

The widespread usage of granite in the building sector motivated us to conduct this research and examine the material’s sustainability in terms of the investigated characteristics. The purpose of this paper is to discuss the statistical analysis results for the mineralogical impact on radiological hazards indices, such as the equivalent of radium, absorbed gamma dose rate, annual effective dose, internal and external hazard indices, as well as the gamma-ray index, that were cal-culated to estimate the environmental risks associated with these granites used as building materi-als, to protect the public from excessive radioactivity exposure. We focused primarily on statistical significance at a 95% confidence level. We employed a non-parametric test (Kruskal–Wallis Test) rather than a one-way ANOVA, to determine the statistical significance of the samples due to the lack of homogeneity or normality among them. To assess the difference between the samples, we used the Mann–Whitney Test on each pair of samples. Additionally, Pearson correlation coefficients for all the mineralogical results are computed. The presence of K-rich minerals (Kefeldspars, biotite) and accessories such as uranophane, uranothorite, allanite, xenotime, fergusonite, aeschynite, zir-con, cassiterite, apatite, and sphene, which are mostly found in granitic rocks, determines the level of natural radioactivity of the investigated granites. Most of the rock samples analyzed have indicators of radioactive dangers that are within the acceptable level range, indicating that they are suitable for use as building materials. On the other hand, some samples have environmental criteria that are higher than international standards, indicating that they are unsuitable for use as construction materials. © 2022 by the authors. Licensee MDPI, Basel, Switzerland. RF 3621/2021 Funding: The work of A.E. and the APC is funded by “Dunarea de Jos” University of Galati, Romania and grant no. RF 3621/2021. The work of A.E. and the APC is funded by ?Dunarea de Jos? University of Galati, Romania and grant no. RF 3621/2021.

The main objective of the present work was to assess the gamma radiation shielding competencies and gamma radiation transmission factors (TFs) for some tellurite glasses in the form of Bi2O3–TeO2–Na2O–TiO2–ZnO. MCNPX general-purpose Monte Carlo code (version 2.6.0) was utilized for the determination of TF values at various well-known radioisotope energies for different glass thicknesses from 0.5 cm to 3 cm. Moreover, some important gamma ray shielding properties were also determined in the 0.015–15 MeV energy range. The results show that glass densities were improved from 5.401 g/cm3 to 6.138 g·cm3 as a function of Bi2O3 increment in the glass composition. A S5 glass sample with the maximum Bi2O3 additive was reported with superior gamma ray shielding properties among the studied glasses. It can be concluded that Bi2O3 can be used as a functional tool in terms of improving glass density and, accordingly, gamma ray shielding attenuation properties of tellurite glasses, where the role Bi2O3 is also critical for other material properties, such as structural, optical, and mechanical. © 2022 by the authors. Licensee MDPI, Basel, Switzerland. This work was performed under Princess Nourah bint Abdulrahman University Researchers Supporting Project Number (PNURSP2022R149), Princess Nourah bint Abdulrahman University, Riyadh, Saudi Arabia. The authors express their sincere gratitude to Princess Nourah bint Abdulrahman University.