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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]

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]

Abstract: Energy dispersive X-ray fluorescence technique (EDXRF) has been employed for measuring L3-subshell absorption jump ratios, and jump factors, for high Z elements. Jump factors and jump ratios for these elements have been determined by measuring L3 subshell fluorescence parameters such as L3 subshell X-ray production cross section , L3 subshell fluorescence yield, , total L3 subshell and higher subshells photoionization cross section . Measurements were performed using a Cd-109 radioactive point source and an Si(Li) detector in direct excitation experimental geometry. Measured values for jump factors and jump ratios have been compared with theoretically calculated and other experimental 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]

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]

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]

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]

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]

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]

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]

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]

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]

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]

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]

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]

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 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 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]