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The research aims to exploring the gamma-ray shielding capacities of polyacrylonitrile/chrome-filled polymer composites through a combination of experimental, theoretical and simulation methods. Additionally, employing MCNPv6 and GEANT4 simulation tools, the study evaluates the materials' performance against neutron radiation. The materials were subjected to various gamma-ray energy levels, and their shielding efficacies are analytically quantified using parameters such as Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), Linear Attenuation Coefficient (LAC), and Half-Value Layer (HVL). At various neutron energies and sample thicknesses, the numbers of transmitted neutrons were evaluated. Notably, composite P0Cr50 (not contain polyacrylonitrile and containing 50% chromium) emerges prominently, demonstrating superior radiation shielding characteristics against both gamma and neutron radiations. This attitude is attributed to its optimal chrome dispersion and density, positioning it as a promising candidate for radiation shielding applications in industrial and nuclear domains. • Composites series including Polymer/Polyacrylonitrile/Chromium were produced. • Gamma and neutron shielding capacities were evaluated. • Experimental, theoretical and simulation methods were used. • An improvement in radiation shielding was observed with increasing Cr amount. • The composite coded as P0Cr50 has the best radiation shielding. [ABSTRACT FROM AUTHOR]

This paper investigates the radiation shielding properties, such as linear and mass attenuation coefficients, half and tenth value layers, effective atomic number and electron density, and radiation protection efficiency as a function of photon energy, of a new composite, PbI2-doped polyester. The mentioned polyester composite was prepared with different proportions of lead(II) iodide (5% increments between 5 and 20%) so that impact of the dopant amount on radiation shielding could be properly analyzed. The prepared composites were tested in 22 different energies in the energy range of 59.5–1408.0 keV with the use of HPGe detector and eight radioactive point sources. The obtained results were further validated by comparing the results of XCOM computer program, and negligible discrepancies were observed. It was observed that PbI2 (20%) composite is more effective gamma radiation shielding material than other produced composites. In light of this information, it can be said that the shielding efficiency increases with increasing lead(II) iodide amount. [ABSTRACT FROM AUTHOR]

The article discusses a study that investigated radiation attenuation characteristics in Bacillus megaterium, Bacillus subtilis and Bacillus simplex from soil samples taken from Diyarbakir, Turkey and in Geobacillus stearothermophilus purchased from Deutsche Sammlung von Mikroorganismen und Zellkulturen. The researchers determined and compared the bacteria's mass attenuation coefficient, molar extinction coefficient, effective atomic number and electron density.

In this study, a novel acrylamide monomer was synthesized and characterized by UV-Vis, FT-IR and 1H NMR measurements. The acrylamide monomer namely, N-(2-acetyl-benzofuran-3-yl)acrylamide (NABA), was prepared in two steps. In the first step, 1-(3-aminobenzofuran-2-yl)ethan-1-one was synthesized by the reaction of 1-chloroacetone with 2-hydroxy-benzonitrile under basic conditions. In the second step, the obtained 1-(3-aminobenzofuran-2-yl)ethan-1-one was reacted with acryloyl chloride and triethylamine at 0–5 °C temperature for obtaining NABA monomer. Then, the structural, vibrational, nuclear magnetic resonance and electronic properties for the synthesized monomer were determined by quantum chemical calculations of DFT method. The results were compared with experimental FT-IR, 1H NMR and UV–Vis spectral data. The band gap of HOMO and LUMO show that the NABA monomer is chemically active and has charge transfer within the monomer. Moreover, molecular electrostatic potential (MEP) maps were drawn to identify reactive regions of NABA monomer. [ABSTRACT FROM AUTHOR]

The gamma ray photon interaction parameters for different samples including calcium silicide, magnesium silicide, magnesium boride, calcium hexaboride, aluminum oxide, and titanium dioxide were investigated. For this aim, the mass attenuation coefficients for these samples were measured by the transmission geometry at 14 energies values (i.e. , E∈[81,1333] keV) and the results were compared with those acquired from the WinXCOM software. From the present samples, calcium silicide and magnesium boride have the highest and lowest effective atomic numbers, respectively. Besides, the effective atomic number values almost remain constant for magnesium silicide. The half value layer results showed that as the energy increases, the probability of photon interaction with the ceramic sample decreases, thus more gamma photons can penetrate the ceramics. • The μ/ρ, Z eff , N E , HVL and MFP parameters were obtained for six ceramic samples. • The experiments were performed using an HPGe detector and six radiation sources. • A good agreement was observed between experimental and theoretical results. • The lowest values of HVL and MFP were found for TiO 2 among the selected samples. • Mg 2 Si sample possesses the highest HVL and MFP values. [ABSTRACT FROM AUTHOR]

Abstract In the present work, the gamma ray shielding performance of Fe/Cr16/Ni72, Fe/Cr21/Ni32.5, Fe/Cr25/Ni20, Fe/Cr18/Ni10 and Fe/Cr17/Ni7 ternary alloys was investigated. In this respect, some important photon shielding parameters such as the linear and mass attenuation coefficients, mean free path, half, quarter and tenth value layers, effective conductivity and effective atomic number for the selected ternary alloys were determined experimentally in the energy range of 81 keV–1333 keV emitted by 22Na, 54Mn, 57Co, 60Co, 133Ba and 137Cs radioactive sources. Besides, the obtained parameters were compared with the calculated values with the help of WinXCOM program based on mixture rule. It is observed that the theoretical results confirmed the experimental results. According to the obtained experimental and theoretical results of all presented parameters, Fe/Cr16Ni72 alloy has the best radiation shielding properties, while Fe/Cr17/Ni7 alloys possesses the worst radiation shielding properties among the selected alloys. Highlights • The radiation protection properties of five ternary alloys were evaluated. • The μ/ρ, μ, MFP, HVL, TVL, QVL and σ parameters were determined. • The experiments were performed using narrow beam geometry. • Fe/Cr16/Ni72 is the best radiation shielding material among the selected alloys. • The μ/ρ results of alloys were compared with those of Pb and ordinary concrete. [ABSTRACT FROM AUTHOR]

The presented work investigates the photon, charged particle and neutron radiation shielding performances of polyester-based composites filled with barite and/or tungsten boride by using experimental, theoretical, and Monte Carlo simulation techniques. The amount of barite/tungsten boride varying from 0 wt% to 50 wt% in the material and polyester resin were exploited as filler and base materials, respectively. Experimental evaluation of BaWB composites has been performed with help of an HPGe detector based gamma spectrometer as well as 22Na, 133Ba, 137Cs and 60Co radioactive point sources with energies in the range of 276.4–1332.5 keV. The experimental data were compared to those theoretically calculated in WinXCOM as well as Monte Carlo (MC) simulations, i.e., MCNP6, GEANT4 and FLUKA codes. The obtained mass attenuation coefficients for the produced composites were in good agreement with the results of MC simulations and WinXCOM software. Comparing to the other polymer composite samples, the sample with the maximum tungsten boride weight percentage has the best radiation shielding property because of having the highest attenuation coefficients and lowest absorption thicknesses. • Ternary composites including Polyester/Barit/Tungsten boride were produced. • Their gamma, charge particle and neutron shielding capacities investigated. • Experimental, theoretical, MCNP6, GEANT4 and FLUKA methods utilized. • Their radiation shielding properties improved with tungsten boride. • BaWB-50 composite has the best radiation shielding among them. [ABSTRACT FROM AUTHOR]

Abstract The aim of this experimental study is to figure out the photon shielding performance of four alloys sample (Ag92.5/Cu7.5, Ag72/Cu28, Pd94/Cr6 and Pd60/Cu40). For this purpose, the shielding ability of these alloys against fourteen photon energies (in the energy range of 81–1333 keV) using six gamma-ray sources (22Na, 54Mn, 57Co, 60Co, 133Ba and 137Cs) was measured and compared with the results obtained by WinXCOM and MCNPX code. The results showed that the measured mass attenuation coefficient values for the four alloys coincide with those calculated by WinXCOM and MCNPX at all energies. The Ag92.5/Cu7.5 sample possesses the highest values of mass attenuation coefficient and effective atomic number. The tendency of the effective conductivity versus photon energy was found as the same as the electron density. Highlights • The μ/ρ, Z eff and N E parameters for some selected alloys were determined experimentally at fourteen different energies. • To verify the experimental values, μ/ρ results were calculated theoretically and MCNPX code. • The measurements were carried out using a high resolution HPGe detector system. • The measured μ/ρ values for the selected alloys coincide with those calculated by WinXCOM and MCNPX at all energies. • The Ag92.5/Cu7.5 sample possesses the highest values of mass attenuation coefficient and effective atomic number. [ABSTRACT FROM AUTHOR]

The effective atomic numbers and electron densities of some synthesized triazoles were determined using the experimental values of total mass attenuation coefficients at 13.93, 17.77, 26.34, and 59.54 keV photon energies. The measurements were performed in a transmission geometry that consists of a Si(Li) detector, an 241Am point source and a target. The measured results were compared with two different theoretical results. The measured results are generally consistent with the theoretical results. It is observed that the measured parameters depend on the photon energy, weighted contributions of the individual atoms within the triazoles, atom number in the triazoles, and chemical composition of triazoles. Also, the effective electron density increases linearly with increasing effective atomic number. [ABSTRACT FROM AUTHOR]

In this study, inorganic compound (Bi 2 (WO 4) 3) was added into the composite to improve the radiation shielding properties of polymer composite. A polymer matrix was prepared by combining unsaturated polyester resin with methyl ethyl ketone peroxide and cobalt octoate (6%), and Bi 2 (WO 4) 3 was added to this polymer matrix at different ratios as filling material. In order to investigate the gamma radiation attenuation properties of the obtained polymer composites, mass attenuation coefficients, radiation shielding efficiencies, radiation transmission factors, linear attenuation coefficients, half values layer, tenth values layer, mean free path values, effective atomic numbers and effective electron densities parameters were obtained. Experimental studies were carried out with the help of HPGe detector at 22 different energies emitted from 22Na, 54Mn, 57Co, 60Co, 133Ba, 137Cs, 152Eu and 241Am radioactive sources in the photon energy range of 59.5–1408.0 keV. Each obtained experimental result was compared with the theoretical results. It was observed that the sample encoded with BiWO20 is the best radiation shielding material among all studied composites (except 59.5 keV). • Polyester based and Bi 2 (WO 4) 3 reinforced composites were produced. • Their gamma radiation shielding properties were investigated. • The studies were carried out experimentally and theoretically. • There was agreement between experimental and theoretical results. • BiWO20 composite has the best radiation shielding among others. [ABSTRACT FROM AUTHOR]

The shielding efficiencies of gamma and neutron radiations for ternary composites containing polyester resin, polyacrylonitrile and gadolinium (III) sulfate at different ratios were investigated in the present study. In order to investigate the gamma radiation shielding capacity of the produced ternary composites, linear and mass attenuation coefficients, half value layer, effective atomic number and radiation protection efficiency parameters were determined experimentally, theoretically and using the GEANT4 simulation code. The gamma shielding capabilities of the composites were studied in the photon energy range of 59.5–1332.5 keV. In order to investigate the neutron shielding abilities of composites, inelastic, elastic, capture and transport numbers, total macroscopic cross section and mean free path parameters were determined with the help of GEANT4 simulation code. In addition, the number of transmitted neutrons at different sample thicknesses and neutron energies were also determined. It was observed that gamma radiation shielding properties were improved due to the increasing amount of gadolinium (III) sulfate and neutron shielding properties were improved due to the increasing amount of polyacrylonitrile. While the composite coded P0Gd50 exhibits a better gamma radiation shielding ability than the others, the neutron shielding of the sample coded P50Gd0 is also more favorable than the others. • Ternary composites containing polyester, C 3 H 3 N and Gd 2 (SO 4) 3 were produced. • Their gamma shielding capacities were determined by three different methods. • Neutron shielding capacities were investigated with GEANT4. • It was observed that gamma shielding properties improved with increasing Gd 2 (SO 4) 3. • It was observed that neutron shielding properties improved with increasing C 3 H 3 N. [ABSTRACT FROM AUTHOR]

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 Z eff 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. • The photon shielding performances of five different borosilicate-based glasses. • MAC, HVL, TVL, MFP, Zeff and EBF were determined for different borosilicate glasses. • The MACs of various borosilicate glasses were estimated using simulation codes. • Finding shows which sample has better photon attenuation performance. [ABSTRACT FROM AUTHOR]

Preventing people and electronic apparatuses from high-energetic nuclear radiation photons has been a significant concern. Due to disadvantages of lead, many studies have been carried out on different materials for several decades. The purpose of this investigation is to exhibit a novel shield design of alloys formed by the combination of W, La and Bi contents as a desired replacement for conventional lead-based absorbers. Photon shielding performances of the investigated alloys have been studied by estimation of mass attenuation coefficient, half-value layer by applying Monte Carlo GEANT4 simulation code and XCOM computer software. Moreover, the EBFs of the alloys were calculated by geometric progression (G-P) fitting formula for photon energy 0.015–10 MeV up to 40 mfp penetration depth. Consequently, the shielding performance of W-3 alloy shows that it is better by a factor of 1.52 and 8.29 than Pb and OC materials, respectively. [ABSTRACT FROM AUTHOR]

The K shell absorption jump ratios, jump factors, effective atomic numbers, and electron densities were derived from the measured total mass attenuation coefficient using an energy dispersive X-ray fluorescence spectrometer for Gd2O3, Gd2(CO3)3H2O, Gd2(C2O4)3H2O, and Gd2(SO4)3 compounds. The total mass attenuation coefficients were measured in the X-ray energy range from 39.52 to 57.14 keV in a transmission geometry utilizing the K α2, K α1, K β1, and K β2 X-rays from different secondary source targets excited by the 59.54-keV photons from an Am-241 annular source and detected by a Si(Li) detector with a resolution of 160 eV at 5.9 keV. The energy gap, ionization energy, electron affinity, and global electrophilicity parameters of oxide, sulfate, oxalate, and carbonate ions were calculated using density functional theory (B3LYP). The experimental results are discussed based on these parameters. Copyright © 2015 John Wiley & Sons, Ltd. [ABSTRACT FROM AUTHOR]

The K α , β and L α 1,2 excitation probabilities for some elements in 56≤Z≤68 at 59.54 keV were obtained using a Si(Li) detector with a multichannel analyzer. It is the first time that the K α , β and L α 1,2 excitation probabilities were determined for the present elements. To obtain the K α , β and L α 1,2 excitation probabilities, the K and L 3 shell/sub-shell absorption jump factors and the K and L 3 shell/sub-shell fluorescence yields were determined experimentally. The measured results of absorption jump factor and fluorescence yield were compared with the theoretical and other experimental results. The determined excitation probabilities were compared only with theoretical calculated ones since there are no other experimental reports for the present elements in the literature. [ABSTRACT FROM AUTHOR]

Barite-doped and polypropylene-based masterbatches were produced at different ratios, and 1 × 1 Rib type weaving process was carried out by obtaining filament yarns. While the morphological and structural properties of the obtained textile products were investigated with XRD, FTIR and SEM, thermal stabilities were investigated with TGA. Then, the shielding abilities of the products against ionizing and electromagnetic radiation were analyzed. The shielding properties against ionizing radiation were studied with mass attenuation coefficient, half value layer, effective atomic number and radiation protection efficiency parameters at nine different energies in the energy range of 17.75 to 81.0 keV. The shielding properties against electromagnetic radiation were studied in the range of 15 to 40 GHz. To test the usability of the products, antibacterial activity tests, breaking strength and elongation tests and surface resistivity tests were carried out. It has been observed that all products are suitable in terms of usability and also, ionizing and electromagnetic radiation shielding properties increase with increasing barite content, and the product containing 10% barite is a good shielding material for radiation compared to others. The data of the present survey can be quite helpful for possible applications such as aerospace, medicine, science, nuclear industry. • Barite-doped and polypropylene-based masterbatches were produced. • 1 × 1 Rib type weaving process was carried out by obtaining filament yarns. • Their shielding abilities for ionizing and non-ionizing radiation were analyzed. • Their characterizations were carried out with XRD, FTIR, SEM and TGA. • Antibacterial activity, breaking strength and elongation tests were carried out. [ABSTRACT FROM AUTHOR]

The paper presents the first measurements of the Kα and Kβ excitation factors for some selected elements from Y to Te. To determine the Kα and Kβ excitation factors, the experimental values of K shell X-ray production cross sections and total absorption photoelectric cross sections were used. The measurements were performed using a Si(Li) detector coupled with 2048 multichannel analyzer and an Am-241 annular radioisotope source which is emitted 59.54 keV γ-photons. It is observed that the Kα excitation factors are 5–6 times larger than the Kβ excitation factors. The measured excitation factors were compared only with theoretical calculated ones since there are no other experimental reports for the present elements in the literature. The present experimental values of Kα and Kβ excitation factors are in satisfactory agreement with the theoretical results. [ABSTRACT FROM AUTHOR]

The total attenuation cross section at the K edge, absorption jump ratio, jump factor, Davisson-Kirchner ratio, and oscillator strength parameters for the K shell were determined by measuring the total attenuation cross sections around the K edge for Pr, Nd2O3, and Sm. The measurements were performed in a secondary excitation geometry using the Kα2, Kα1, Kβ1, and Kβ2 X-rays (in the region from 31.817 to 55.293 keV) from different secondary source targets excited by the 59.54 keV γ-photons from an 241Am annular source. It is the first time that the Davisson-Kirchner ratio values have been determined for present samples. The experimental results were compared with the theoretically calculated and other available experimental results. [ABSTRACT FROM AUTHOR]

The L i ( i = l, α, β, γ) X-ray production cross section and Lα/Ll, Lα/Lβ, Lα/Lγ, Ll/Lβ, Ll/Lγ, and Lβ/Lγ intensity ratio values for Yb, Ta, W, Hg, Tl, Pb, Bi, Th, and U have been determined using an excitation geometry at 59.54 keV incident photon energy. The measurements were performed using an Am-241 annular radioactive source and a high resolution Si(Li) detector. The experimental results of L i X-ray production cross sections and intensity ratios were compared with three different theoretical results and other available experimental results in the literature. Reasonable agreement is typically observed between the present and theoretical results. [ABSTRACT FROM AUTHOR]

The effective atomic numbers and electron densities of some samarium compounds were determined using the experimental total mass attenuation coefficient values near the K edge in the X-ray energy range from 36.847 up to 57.142 keV. The measurements, in the region from 36.847 to 57.142 keV, were done in a transmission geometry utilizing the Kα 2 , Kα 1 , Kβ 1 and Kβ 2 X-rays from different secondary source targets excited by the 59.54 keV gamma-photons from an Am-241 annular source. This paper presents the first measurement of the effective atomic numbers and electron densities for some samarium compounds near the K edge. The results of the study showed that the measured values were in good agreement with the theoretically calculated ones. [ABSTRACT FROM AUTHOR]

In this study, brass (Cu/Zn) reinforced polymer composites with different proportions of brass powders were fabricated. Different types of nuclear shielding parameters such as mass and linear attenuation coefficients, radiation protection efficiency, half and tenth value layers, and effective atomic number values were determined experimentally and theoretically in the energy range of 0.060–1.408 MeV in terms of gamma-ray shielding capabilities of fabricated polymer composites. A high Purity Germanium detector (HPGe) in conjunction with a Multi-Channel Analyzer (MCA) and twenty-two characteristic gamma-ray energies have been used in the experimental phase. In addition, the exposure and energy absorption buildup factors of reinforced Cu/Zn composites were calculated, and relative dose distribution values were computed to verify them. Proton mass stopping power (ΨP), proton projected range (ΦP), alpha mass stopping power (ΨA), and alpha projected range (ΦA) parameters, which indicate the interactions of the produced composites with charged particle radiation, were investigated. Fast neutron removal cross-section (ΣR) results were determined to give an idea in terms of neutron shielding. According to the obtained results, it is reported that the CuZn20 coded sample's ability to attenuate gamma-ray and charged particle radiation is more efficient than that of other prepared composites. A CuZn05 coded sample was found to be more suitable for neutron shielding capability. [ABSTRACT FROM AUTHOR]

Detailed investigations on the photon and neutron attenuation properties of various BiBr 3 and PbSO 4 incorporated polyester composites have been carried out in terms of evaluating their potential use as new radiation shielding materials. Utilizing HPGe detector-based γ-ray spectrometry, the mass attenuation coefficient values of the polyester materials were calculated over a wide photon energy range of 59.5–1408 keV. The experimental results have been compared to those obtained using XCOM software and showed that the measured attenuation coefficient was in good agreement with the theoretical results at all photon energies studied. Moreover, BiBr 3 (20%) and PbSO 4 (20%) exhibit the minimum half value layers (5.94 and 6.58 cm at 661 keV) and highest radiation protection efficiencies (69.80 and 69.67% at 59.9 keV), while the neutron removal cross-sections of BiBr 3 (5%) and PbSO 4 (5%) samples were higher than the other composites studied. • The radiation shielding properties for some doped polyester composites have been investigated. • Experiments were performed over a wide photon energy range of 59.5–1408 keV. • The experimental results were supported using theoretical studies. • BiBr 3 (20%) and PbSO 4 (20%) samples exhibit the best radiation shielding properties. [ABSTRACT FROM AUTHOR]

In this study, the gamma radiation shielding properties of concrete samples reinforced with 10%, 20%, 30%, 40% and 50% of the cement weight of brass alloy were investigated. To test gamma shielding performance of the samples, mass and linear attenuation coefficients, half and tenth value layers, effective atomic number and radiation protection efficiency parameters were determined experimentally, theoretically and Monte Carlo simulations (GEANT4 and FLUKA). The studies were performed at 11 different gamma energies that range from 59.5 to 1332.5 keV emitted from 22Na, 60Co, 133Ba, 137Cs and 241Am radioactive sources. The obtained results showed that the gamma shielding property of the samples increases with increasing brass alloy amount, and the sample reinforced with 50% brass alloy was the most effective one to shield gamma radiation. Neutron shielding properties of the sample reinforced with 50% brass alloy were therefore investigated by adding 5%, 10%, 15% and 20% boron carbide (B 4 C). The neutron permeability, which is an important parameter in terms of the neutron shielding performance of B 4 C added concrete samples, was investigated by using GEANT4 and FLUKA simulation programs. While the total macroscopic cross section results obtained with GEANT4 for concretes coded as P0, P50, P50B5, P50B10, P50B15 and P50B20 are 2.0290, 2.0324, 2.0343, 2.0346, 2.0361 and 2.0367 cm-1, respectively, the results obtained with FLUKA are 2.0287, 2.0322, 2.0337, 2.0342, 2.0357 and 2.0362 cm-1, respectively. Therefore, the sample containing 20% B 4 C is the sample that best shields neutron radiation. In addition to the radiation shielding properties of the produced samples, the mechanical properties such as compressive strength, Schmidt surface hardness, ultrasound pulse velocity were also tested in terms of usability. • The concretes reinforced with brass/brass + B 4 C were produced. • Their mechanical and ionizing radiation shielding properties have been determined. • The mechanical and gamma shielding properties improved with increasing brass. • The neutron shielding capacity improved with increasing B 4 C. • P50 and P50B20 were determined the best for γ and neutron shielding, respectively. [ABSTRACT FROM AUTHOR]

This paper has been focused on the a detail study on non-ionizing and ionizing electromagnetic (EM) shielding features and build-up factors of reinforced with ferrochrome (FeCr) composites. The non-inozing electromagnetic shielding performance quantities of composites have been determined in the frequency range between 12.4 and 18.0 GHz. Also, the experimental mass attenuation coefficients (MAC) have been estimated using gamma spectrometer and various radioactive point, and compared to those of theoretical and simulation (MCNPX) results. With help of the obtained linear attenuation coefficients, several attenuation quantities, i.e., effective atomic number (Z eff), half value layer (HVL), and mean free path (MFP) have been discussed. In addition, buildup factors (EBF and EABF) values have been estimated utilizing the G-P fitting method. The results showed that composite encoded FeCr(15%) is superior shielding attenuation properties among the investigated samples. • Composites reinforced with FeCr with three different ratios were produced. • Their electromagnetic shielding features were investigated between 12.4 and 18.0 GHz. • γ-ray shielding properties were investigated experimentally in a wide energy range. • EBF and EABF results of composites were calculated in the range of 0.015–15 MeV. • FeCr(15%) is the best radiation shielding material among the selected samples. [ABSTRACT FROM AUTHOR]

Polyester is strong and durable material and tends to retain its shape, thus polyester composites have become highly preferred option in high-tech applications. This motivates the usage of polyester composites in the production of radiation shielding materials as well. In present study, gamma ray shielding properties of polyester composite reinforced with different proportions of Cadmium Telluride (5%, 10%, 15% and 20%) have been investigated theoretically and experimentally. The experiments were performed with the use of HPGe detector in a wide range of photon energies varying from 59.5 to 1408.0 keV while XCOM computer program was computed in the same photon energy range to obtain theoretical results and to verify the experimental outcomes. Remarkable radiation protection efficiency was obtained with additive material of Cadmium Telluride, and the radiation protection efficiency was found to be increased with the increase of additive material amount. Negligible discrepancies between experimental and theoretical results were also observed. Image 1 • Polyester composites reinforced with CdTe were produced for the first time. • The gamma-ray attenuation capacities of the composites were investigated. • Experimental and theoretical studies were carried out in a wide energy range. • Remarkable radiation protection efficiency was obtained with additive of CdTe. • CdTe(20%) coded sample has better gamma-ray attenuation than other samples. [ABSTRACT FROM AUTHOR]

In the present study, iron (Fe)-reinforced novel composite materials were produced as alternative shielding materials. In this context, linear attenuation coefficients and mass attenuation coefficients (MAC), half- and tenth-value layers, mean free path (MFP) and effective atomic number were determined. An experimental gamma-ray transmission setup was utilized for determination of MAC values. To confirm the consistency of experimental results, the obtained MAC values were compared with those produced using the WinXcom program and MCNPX Monte Carlo code. Moreover, exposure buildup factors and energy absorption buildup factors were calculated using a geometric progression fitting method. Relative dose distribution values of fabricated samples were calculated at 5, 10 and 20 MFP penetration depths up to 10 MeV. In addition to gamma-ray attenuation properties, basic interaction parameters of charged particles such as protons and alpha mass stopping powers, alpha projected ranges and proton projected ranges were determined in the 0.015–15 MeV energy range. Finally, variation of fast neutron removal cross-section versus increasing Fe concentration in composites was investigated. The composite with the highest Fe addition (20%) showed the best shielding capacity for gamma radiation. • Iron (Fe)-reinforced novel composite materials were produced. • An experimental gamma-ray transmission setup was utilized for determination of MAC values. • EBF and EABF calculated using geometric progression fitting. • MAC values were compared with WinXcom program and MCNPX Monte Carlo code. • Fe-20 with the highest Fe addition had the best gamma-ray radiation shielding capacity. [ABSTRACT FROM AUTHOR]

Various composite shielding materials have favorable structural, mechanical, physical, and nuclear properties, besides their economic affordability. Such properties have widened the usage of composites around the globe in large-scale installations such as nuclear medical facilities, nuclear power plants, and spent nuclear fuel storage. In the current study, two groups of polymer composites have been prepared and their gamma-ray attenuation characteristics have been investigated both experimentally and theoretically. Four samples of each group have been prepared by varying the doped material (BaTiO 3 and CaWO 4) percentage between 5% and 20% with increments of 5%. To investigate the gamma-ray attenuation features, the linear attenuation coefficient, radiation protection efficiency, half value layer, mean free path, and effective atomic number parameters for these polymer composites reinforced with BaTiO 3 and CaWO 4 were obtained in the energy range between 59.5 and 1408.0 keV (at 22 different energies) using narrow beam transmission geometry. The experiments were performed with the aid of an HPGe detector and eight different radioisotope point sources. According to the experimental and theoretical results, BaTiO 3 (20%) and CaWO 4 (20%) have better gamma-ray attenuation properties than the other prepared polymer composites. Moreover, CaWO 4 (20%) has better gamma-ray attenuation features than BaTiO 3 (20%). [ABSTRACT FROM AUTHOR]

Shielding capacities of gamma and neutron radiations of concrete samples with bronze addition and boron carbide at different rates were investigated within the scope of this study. In order to examine the gamma radiation shielding capacities of the produced bronze doped concrete samples, linear attenuation coefficients mass attenuation coefficients, half thickness values layer, one-tenth thickness values layer, effective atomic number and radiation protection efficiency parameters were analyzed using experimental, theoretical (WinXCOM) and simulation (GEANT4 and FLUKA) codes. The gamma radiation shielding capacities of the produced concrete samples were investigated at different energies ranging from 59.5 to 1332.5 keV. The results showed that increasing the amount of bronze in the produced sample attenuated more amount of gamma comparing to the samples that had less bronze. The best sample among the produced concretes was found to be the sample that doped with 50% bronze. Then, different proportions of boron carbide (B 4 C) were substituted into the sample content (50% bronze) to produce a new concrete doped with bronze and B 4 C. The neutron shielding abilities of the new concrete samples produced in this way were investigated with the GEANT4 and FLUKA simulation codes. Using different thicknesses and energies the neutron shielding property of the samples was analyzed to test neutron transmission. The results showed that the sample doped with 20% boron carbide was the best attenuator against neutron radiation. • Bronze and B 4 C doped concrete samples were produced. • Gamma and neutron radiation capabilities of the produced concrete samples were investigated. • Gamma radiation shielding parameters of the produced samples were determined experimentally. • Neutron shielding capacities were investigated with GEANT4 and FLUKA. • Gamma radiation shielding properties improved with increasing bronze amount. [ABSTRACT FROM AUTHOR]

The aim of this study is to evaluate gamma ray shielding properties for bismuth doped barite-based ternary polymer composite materials. In the first stage of the study, a polymer matrix was prepared by combining orthophthalic unsaturated polyester resin (OUP), Methyl Ethyl Ketone Peroxide (MEKP) and Cobalt Octoate (6%) (Co-6). Then, barite and bismuth were added in certain proportions as filler material into this polymer matrix and thus ternary composites were produced. Experimental studies for the produced samples were carried out in narrow beam geometry using HPGe detector and 133Ba, 22Na, 137Cs, 60Co radioactive sources which emit photons between 276.4 and 1332.5 keV energy. To determine the gamma ray shielding properties of the produced ternary composites, radiation protection efficiency (RPE), linear attenuation coefficient (μ), mass attenuation coefficient (μ/ρ), half value layer (HVL), tenth value layer (TVL), mean free path (MFP), effective atomic number (Z eff), effective electron density (N E) parameters were obtained. Experimental results were compared with theoretical results obtained with WinXCOM software and GEANT4 Monte Carlo simulation code. Experimental and theoretical results were found to be compatible with each other. According to obtained results, it was found that the sample with the best shielding property among the prepared samples was BaBi50 coded sample. • Barite-based ternary composites were fabricated. • Their gamma shielding capacities were investigated. • Experimental, theoretical and GEANT4 methods were used. • Good agreement was observed between the used methods. • The composite coded as BaBi50 provided better shielding than the other. [ABSTRACT FROM AUTHOR]

This study investigates the radiation shielding properties of composites containing polyester resin, boron carbide and titanium oxide in varying proportions. The radiation transmittance of the produced composites was measured using radioactive sources 241Am, 137Cs, 133Ba, 60Co, and 22Na across a photon energy range of 59.5 keV–1332.5 keV. To analyze radiation permeability, experimental geometry was simulated using Monte Carlo-based computer codes Monte Carlo N-Particle (MCNP), Particle and Heavy Ion Transport code System (PHITS) and FLUktuierende KAskade or Fluctuating Cascade (FLUKA), and the experimental data were compared with simulation results and theoretical data obtained from WINXCOM. The findings demonstrated a high degree of consistency between experimental, simulation, and theoretical results. Notably, the BCTiO50 sample, which included a 50% addition of TiO 2 , emerged as the most effective in photon radiation shielding. In addition to gamma shielding, the neutron shielding properties of the produced composites were evaluated using the FLUKA code, revealing that the BCTiO0 sample, with the highest percentage of boron, provided the best neutron shielding. This analysis included composites with decreasing boron carbide content by 10%, 20%, 30%, 40%, and 50% by weight, each replaced with titanium oxide, showcasing the potential applications of these polymer composites in radiation shielding. • Ternary composites containing polyester resin/BC4/TiO2 were produced. • The shielding characteristics were investigated in a wide gamma energy range. • Their neutron shielding was obtained at different energies and thicknesses. • The experimental, theoretical and simulation studies were carried out. • BCTiO50 and BCTiO0 were suggested for gamma and neutron shielding, respectively. [ABSTRACT FROM AUTHOR]

The usage of composites as the shielding materials are highly recommended since they could be used in order to attenuate the undesired radiation with unique properties and advantages in the areas where the radiation is prevalent. In this context, not only are their radiation shielding properties important but also their flexibility, durability and low cost. Due to the mentioned superior characteristics, the polyester based composites are among the most preferred materials. With the aim of creating unique and novel radiation shielding materials, this study investigates gamma and neutron shielding capabilities of the polyester composites reinforced with Boron and Tin nanopowders at different proportions (0–50%, 10–40%, 20–30%, 30-20% and 40-10%, 50-0%). The gamma shielding abilities of the prepared polyester composite materials were evaluated using an HPGe detector system, WinXCOM computer program and different simulation tools (FLUKA and GEANT4) at the energies varying from 59.5 to 1332.5 keV. The experimental, theoretical and simulation results showed remarkable agreement between each other, and the addition of Sn enhances the gamma attenuation performance of the chosen polyester composite materials. In addition to gamma analysis results, neutron shielding properties of the proposed composites are further determined. On this purpose, the transmitted neutron numbers through the samples (as functions of neutron energy and the sample thickness) and effective neutron removal cross sections were evaluated. The neutron shielding performance of the samples showed that the prepared composites could be alternative materials to the existing neutron shields in the literature. • The polyester composites reinforced with boron and tin nanopowders are produced. • The gamma attenuation abilities of the prepared composites are evaluated. • HPGe detector, WinXCOM program and MC simulations are used for gamma analysis. • Theoretical and simulation methods are used for the neutron shielding tests. • The proposed composites show excellent gamma and neutron shielding performance. [ABSTRACT FROM AUTHOR]

The aim of this study is to evaluate both buildup factors and photon attenuation effectiveness of some borate glasses doped by Cd, Fe, V, and Bi. The mass attenuation coefficients (μ m) of these glass systems have been calculated via MCNP6 and GEANT4 computer simulation codes over 0.02–10 MeV energy range and compared with the theoretical results of WinXCOM program. And then, half-value layer, (HVL), mean free path (MFP), and effective atomic number (Z eff) for the different content based glasses have been determined. Through G-P fitting process, exposure buildup factors (EBF) have been found in the energy range of 0.015–15 MeV up to 40 mfp. It can be concluded that SrBiO20 glass is alternative material in terms of photon attenuation, respectively. • Buildup factors and photon attenuation parameters of some borate glasses doped by Cd, Fe, V, and Bi have been investigated. • Monte Carlo simulations and theoretical calculations have been done. • SrBiO20 glass is alternative material in terms of photon attenuation. [ABSTRACT FROM AUTHOR]

The anisotropy parameter values β of the L shell fluorescent X-rays (Lι (L3-M1), Lβ6 (L3-N1), Lα1,2 (L3-M5,4) and Lβ2,15 (L3-N5,4) of Bi, Pb, Ta, Lu, and Yb excited by 22.6 keV photons were measured. These values were used to determine the kinematic coefficient ratios α(Lι/Lα1,2), α(Lι/Lβ6), and α(Lα1,2/Lβ2,15). The Lι and Lβ6 X-rays were found to be anisotropically emitted whereas Lα1,2 and Lβ2,15 X-rays showed less anisotropic spatial distributions. Also, the polarization degrees of Lι and Lα X-rays were measured for the present elements and observed that the Lι lines were found to be strongly polarized whereas the Lα lines showed less polarization. [ABSTRACT FROM AUTHOR]

Abstract: In this work, L X-ray fluorescence cross sections, L sub-shell fluorescence yields and level widths and radiative vacancy transfer probabilities of L sub-shells to M i , N i and O i sub-shells were measured for the elements Ho, Lu, W, Hg and Bi. Energy dispersive X-ray fluorescence (EDXRF) technique was used to measure L X-ray photons. To obtain related parameters, we used 59.54keV gamma photons of 241Am radioactive point source. Emitted L X-ray photons from targets were collected by means of a Si(Li) detector with resolution of 180eV at 5.9keV. The present results are generally in a good agreement with theoretical calculations and the other results obtained in the literature, within their range considering experimental uncertainty. [Copyright &y& Elsevier]

Abstract: The , and subshell X-ray production cross sections for U, Th, Bi, Pb, Tl, Hg, Au, Pt, Os, W, Ta, Lu, Yb and Er have been measured at 22.6keV incident photon energy. The measurements were performed using a 109Cd radioisotope as the photon source and a Si(Li) detector. L i subshell fluorescence yields ω 1, ω 2 and ω 3 have been determined from the measured , and subshell X-ray production cross sections. The measured L i subshell production cross sections and ω i fluorescence yields were compared with theoretical, the semi-empirical and recommended values. [Copyright &y& Elsevier]

Abstract: The L X-ray fluorescence cross sections (σ L1, σ Lα, σ Lη , σ Lβ, σ Lβ6, σ Lβ2,4,15, σ Lβ1,3, σ Lγ , σ Lγ1, σ Lγ2,3,6,8, σ Lγ4,4′ and σ Lγ5) and I Lα /I Li (i=l, η, β 6, β 2,4,1,5, β 1,3, γ, γ 1, γ 2,3,6,8, γ 4,4′ and γ 5 intensity ratios for some elements in the atomic range 66≤Z≤92 have been measured at 22.6keV photon energy emitted from a 109Cd radioactive point source. The L X-rays emitted by samples have been counted by a Si(Li) detector. The L X-ray fluorescence cross sections and intensity ratios have also been calculated theoretically by using atomic parameters. The measurement results have been compared with available data and the theoretical values. Within experimental deviations, our data are in good agreement with the available data and the theoretical values. [Copyright &y& Elsevier]

Purpose: Hepatitis C virus (HCV) is prevalent in renal insufficient patients. The aim of the present study was to evaluate the efficacy and tolerability of pegylated interferon alpha-2a (peg-IFN-alpha-2a) among these patients.Methods: Among 437 patients within total hemodialysis population in hemodialysis units, in total 83 patients (19.0%) were anti-HCV positive and of these 83 patients, 33 (39.7%) were HCV-RNA positive. Treatment was initiated in 33 patients who had chronic HCV infection. All patients were found to be HCV-RNA positive. During treatment, peg-IFN-alpha-2a (40 kDa), 135 microg/week was used on these 33 patients.Results: Twenty-six (78.8%) of the 33 patients enrolled in the study completed the treatment. Two patients (6.0%) did not complete treatment because they had serious adverse events such as anemia and thrombocytopenia. At the onset of treatment, while all of 26 patients were HCV RNA positive, HCV RNA turned to negative in all 26 patients 3 months after treatment.Conclusions: At the end of the study, peg-IFN-alpha-2a treatment of patients with chronic hepatitis C on maintenance hemodialysis may improve prognosis and their quality of life. [ABSTRACT FROM AUTHOR]

Osteosarcoma of the cranial facial region is uncommon and only rarely involves the ethmoid or sphenoid bones. The authors report on an unusual case of a 17-year-old male presenting with chondroblastic osteosarcoma of the maxillary, ethmoid, and sphenoid sinuses who remains well and disease-free at 46 months. He was treated with anterior craniofacial resection followed by postoperative radiotherapy to the sight of the primary tumor. He did not receive chemotherapy because of emerging hepatitis-B infection and vasculitis. The literature on extragnathic craniofacial osteosarcomas is reviewed with particular emphasis on treatment options of this rare tumor. [ABSTRACT FROM AUTHOR]

The present study is extremely associated with the evaluation of cathode ray tube (CRT) waste which is a growing hazardous waste management and disposal issue. The Er-added recycled glasses derived from CRT have been successfully fabricated as a component for Na 2 O–Al 2 O 3 –SiO 2 –K 2 O–CaO–SrO–BaO–PbO–Fe 2 O 3 –TiO 2 –Er 2 O 3 glass systems. The waste cathode ray tube panel glass (WPG) series were obtained by inserting the Er 2 O 3 in substitution for CRT in the amounts of 0, 1, 3 and 5 mol%. The synthesized WPG series were then subjected to numerous characterization analysis. One can firmly report that the insertion ratio from 0 to 5 mol% in Er 2 O 3 increased the glass density from 2.9216 to 2.9763 g/cm3. Further, there exists no crystalline formation with the addition of Er 2 O 3 , instead, an amorphous nature in all WPG series emerges. Microstructural images captured by the SEM technique also confirm the non-crystallinity of the fabricated samples. Energy dispersive spectroscopy (EDS) in SEM, besides, paved the way for revealing the elemental mapping of the WPG series. From the perspective of radiation shielding competencies, nuclear shielding features have been evaluated in terms of μ m and related attenuation parameters at several photon energies of 276.4–1332.5 keV by utilizing narrow beam transmission methods. The experimental data have been also confirmed to those of theoretical results by WinXCom software. The HVL results revealed superior photon radiation shielding performances for recycled WPG glasses in comparison to various concretes. In addition, exposure buildup factor (EBF) values estimated utilizing the G-P fitting approach would be useful to design or develop the synthesized glass systems for shielding applications. Furthermore, the macroscopic effective removal cross-sections for fast neutron (Σ R) have been estimated. In conclusion, the findings clearly demonstrated that Er-incorporated CRT glasses can effectively be implemented in radiation shielding applications instead of Pb having toxic effects. [ABSTRACT FROM AUTHOR]

This study presents gamma-shielding characteristics of Li 2 WO 4 doped polyester composites. In the study, unsaturated polyester was chosen as resin, Li 2 WO 4 was chosen as filling material, cobalt octoate 6% (CO-6) and methyl ethyl ketone peroxide (MEKP) were respectively chosen as accelerator and initiators. Four different samples with 5%, 10%, 15% and 20% Li 2 WO4 were prepared and the prepared samples were tested by using 22Na, 54Mn, 57Co, 60Co, 133Ba, 137Cs, 152Eu and 241Am radioactive point-isotropic sources and one gamma spectrometer system based HPGe detector. The experimental results were obtained with the help of the transmission geometry between 59.5 and 1408.0 keV photon energies. For the validation of the results, the test results were compared with the results obtained by WinXCOM computer program and both results showed good agreement. It was observed that the mass attenuation coefficients lie within the range of 0.3042–0.0558 cm2 g-1 for Li 2 WO 4 (5%), 0.4074–0.0556 cm2 g-1 for Li 2 WO 4 (10%), 0.5042–0.0555 cm2 g-1 for Li 2 WO 4 (15%) and 0.5909–0.0553 cm2 g-1 for Li 2 WO 4 (20%) in the energy range of 59.5–1408.0 keV. Comparing to the other Li 2 WO 4 (5%, 10%, 15%) contents, Li 2 WO 4 (20%) was found to have the higher radiation shielding property. This shows that the radiation protection performance of unsaturated polyester increases when Li 2 W0 4 is added as filler. • Four Polyester/Li 2 WO 4 composite samples with different percentage were prepared. • The radiation attenuation properties of these samples were investigated. • Experimental measurements were performed over a wide photon energy range. • Theoretical results were checked with experimental results. • Li 2 WO 4 (20%) sample is better for photon shielding comparing to the other samples. [ABSTRACT FROM AUTHOR]

The preparation of materials with high attenuation performance is one of the major issues in the radiation shielding applications. This study is based on the investigation of gamma-shielding performances of various polyester composites reinforced with Zn. Utilizing gamma spectrometer based on HPGe detector, the mass attenuation coefficient (μ/ρ) of the present composites was measured at various photon energies between 59.5–1408 keV. The obtained experimental data were confirmed with those of MCNPX code as well as XCOM program. It is found that the attenuation coefficient values of the studied composites are in good agreement with the results of other approaches at the investigated energies. The best photon-shielding effectiveness was observed in the composite tagged with Zn (10%). The shielding characteristics of composite enhances with the addition of Zn as filler. [ABSTRACT FROM AUTHOR]

This work presents a detailed radiation shielding study for polymer composites filled with Boron and Molybdenum additives. The chosen novel polymer composites were produced at different percentages of the additive materials to provide a proper evaluation of their neutron and gamma-ray attenuation abilities. The effect of additive particle size on the shielding characteristics was further investigated. On the gamma-ray side, simulation, theoretical and experimental evaluations were performed in a wide range of photon energies varying from 59.5 keV to 1332.5 keV with help of MC simulations (GEANT4 and FLUKA), WinXCOM code, a High Purity Germanium Detector, respectively. A remarkable consistency was reported between them. On the neutron shielding side, the prepared samples produced with nano and micron particle size additives were additionally examined by providing fast neutron removal cross-section (Σ R) and the simulated neutron transmissions through the prepared samples. The samples filled with nano sized particles show better shielding capability than the one filled with micron sized particles. In other words, a new polymer shielding material that does not contain toxic content is introduced: the sample codded N–B0Mo50 exhibits superior radiation attenuation. • Unsaturated polyester is mixed with boron and molybdenum nano and micropowders. • The gamma and neutron shielding abilities are studied for nano-micron additives. • HPGe detector, WinXCOM program and MC simulations are used for gamma analysis. • Theoretical and simulation methods are used for the neutron shielding evaluation. • The proposed composites show excellent gamma and neutron shielding performance. [ABSTRACT FROM AUTHOR]

Abstract: Purpose: The effect of sirolimus (SRL) in renal function was studied in renal transplant recipients. Patients and Methods: We studied 20 patients who underwent live related kidney transplantation 1 to 2 years prior under cyclosporine (CsA) treatment and displayed serum creatinine values between 2 and 3 mg/dL. The patients were randomized into 2 groups prospectively. The calcineurin inhibitors (CNI) group continued taking CsA; the SRL group underwent a switch from CsA to SRL. Biopsies were performed to assess chronic allograft nephropathy (CAN) findings and TGFβ1 in the transplanted kidneys at the beginning and the end of the study. Creatinine clearance, serum creatinine, and proteinuria values were detected in the beginning as well as at 1, 3, 6, and 12 months later. Results: At the beginning of the study, the creatinine clearance and serum creatinine levels were 52.21 mL/min and 2.05 mg/dL in the CNI group and 47.76 mL/min and 2.13 mg/dL in the SRL group, respectively. At 12 months, these values were 48.11 mL/min and 2.57 mg/dL in the CNI group and 50.45 mL/min and 2.12 mg/dL in the SRL group, respectively. Creatinine clearance values between the 2 groups at 12 months were statistically different. Although it was not significant, there was a tendency toward decreases inflammatory infiltration and TGFβ1 levels in the SRL group compared with the CNI group on the second biopsies. Conclusion: Pathologic findings of CAN development, serum creatinine, and creatinine clearance values were ameliorated in the SRL group. We concluded that SRL positively affected long-term graft survival. [Copyright &y& Elsevier]

This work is part of an ongoing project to produce environmentally friendly alternative radiation shielding materials for ionizing radiation facilities such as medical and industrial areas. As a new shield, a series of Sodium Dodecatungstophosphate Hydrate (Na 3 PO 4.12WO 3.H 2 O) doped polymer composite materials with different additives have been successfully produced. The hypothesis is highlighted by the positive effect of Na 3 PO 4.12WO 3.H 2 O supplement for nuclear radiation shield efficiency. The nuclear shielding performance of the new polymer composite materials produced was calculated using the WinXcom theoretical program at different energies. The results obtained were compared with the results calculated using the MCNP-X simulation program. In addition, a wide range of shielding parameters for gamma, neutron, proton and alpha radiation. For gamma radiation, mass attenuation coefficients (μ m), half value layer (HVL), tenth value layer (TVL), mean free path (MFP), linear attenuation coefficients (LAC), effective atomic number (Z eff), exposure (EBF) and energy absorption buildup factors (EABF), dose multiplication factor (K(E,X)), the radiation protection efficiency (RPE) were evaluated; for neutron radiation, fast neutron removal cross sections (Σ R) was calculated; for proton and alpha radiation, Proton mass stopping power (Ψ P), proton projected range (PR - Φ P), alpha mass stopping power (Ψ A) and alpha projected range (PR - Φ A) have been determined. Among the mentioned shielding parameters, lower values of HVL, TVL, MFP, EBF, EABF, MSP, PR and high μ m , Z eff , Σ R imply that the composite material has better shielding properties. According to the obtained results, it is reported that the NPW20 coded sample's ability to attenuate gamma and charged particle radiation more efficiently than that of other prepared composites. NPW05 coded sample was found to be more suitable for neutron shielding capability. Image 1 • Novel polymer composite materials have been fabricated. • Nuclear shielding characterization was performed. • The experimental results were compared with MCNPX and WinXCOM data. • NPW25 sample has an excellent nuclear radiation shielding ability for charged particles and gamma ray. • NPW05 sample has better protection for neutrons. [ABSTRACT FROM AUTHOR]

This study investigated the radiation shielding capacity of undoped polymer composite and lead (II) chloride (PbCl 2)-containing polymer composite samples. The PbCl 2 and polyester resin were used as filler and base materials, respectively. The PbCl 2 was added to the polyester resin from 5 wt% to 20 wt%, and so an undoped polymer composite and four polymer composite samples each with different PbCl 2 /polymer resin ratios were investigated for their radiation attenuation capacity. Experimental data of the samples were taken using an HPGe detector, and 241Am, 133Ba, 57Co, 22Na, 137Cs, 152Eu, 54Mn and 60Co radioactive point sources were used with energies in the range of 59.5–1408.0 keV. The experimental data were compared with both those simulated with FLUKA code and those theoretically calculated in WinXCOM. Mass attenuation coefficients used in estimating the shielding capacity of the samples were in good agreement with those found using FLUKA and WinXCOM. Radiation protection efficiency was improved by 244% especially at 59.5 keV energy by using PbCl 2 (20%) polymer composite compared to undoped polymer composite. The sample with the maximum weight percentage of PbCl 2 , PbCl 2 (20%), had the highest attenuation coefficients and lowest absorption thicknesses, and had the best radiation shielding property compared to the other polymer composite samples. • The gamma photon shielding capacities of some polymer composites were investigated. • Experiments were performed using an HPGe detector and eight radioactive sources. • Experimental μ/ρ values were checked against those of FLUKA and WinXCOM results. • Radiation protection efficiency was improved by 244% at 59.5 keV by adding PbCl 2. • PbCl 2 (20%) had the best radiation shielding property among the prepared composites. [ABSTRACT FROM AUTHOR]