Search

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]

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]

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]

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]

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]

In the present work, the radiation shielding proeprties of lithium borophosphtellurite glass system with the composition of (100-x) [0.5Li 2 O-0.1B 2 O 3 –0.4P 2 O 5 ]-xTeO 2 (x = 0, 10, 20, 30 and 40 mol%) were reported. The mass attenuation coefficient (μ/ρ) of the selected glass system (LiBPTe0, LiBPTe10, LiBPTe20, LiBPTe30 and LiBPTe40) was calculated at 356 keV, 662 keV, 1173 keV and 1330 keV photon energies by using Geant4 and FLUKA codes and the results were compared to the values obtained theoretically using WinXcom software. The correlation theory has been used to calculate the correlation coefficients (R2) between the results from WinXcom and the both simulations codes (Geant4 and FLUKA) for each sample. Moreover, some other radiation shielding parameters such as effective atomic number, photon transmission, mean free path and half value layer were calculated. The gamma photon transmission results showed that the transmission values of the 356 keV photons are lower than those of energies 662, 1173 and 1330 keV. At 356 keV, the transmission value for LiBPTe0 (at 6 cm thickness) is found to be 0.245 while at the same energy and thickness the transmission value is 0.088 for LiBPTe40. Out of all the glasses considered in present work, LiBPTe40 possesses the highest values of effective atomic number (Z eff). The Z eff values for the present glasses are 8.02, 9.55, 11.16, 12.85 and 14.64 for LiBPTe0, LiBPTe10, LiBPTe20, LiBPTe30 and LiBPTe40 respectively at 356 keV. The mass attenuation coefficient and effetive atomic number results showed that utilization 40% mol of TeO 2 significantly improves the gamma ray shielding properties of the selected glass system. The shielding effectiveness of the selected samples was compared with other reference materials namely two radiation shielding glasses and four concretes used in different shielding purposes in terms of the mean free path (MFP) at 356 keV. The results revealed that the MFP of RS-253-G18 is lower than LiBPTe0sample. Moreover, the MFP of ordinary concrete is higher than the MFP of all glasses under examination, thus the investigated tellurite glasses have better attenuation features than the ordinary concrete. • μ/ρ values were calculated using Geant4 and FLUKA. • The maximum number of photons penetration through glass sample occurs at 1330 keV. • LiBPTe40 and LiBPTe0 possess highest and lowest values of Z eff. • The transmission decreases with the addition of TeO 2 in glass composition. [ABSTRACT FROM AUTHOR]