Aluminum, boron, and magnesium are one of the most common aerospace infrastructure materials. Therefore it is important to know their effectiveness in radiation shielding. In this study, Al–B–Mg ...powder alloy with a nominal composition of Al
50
B
25
Mg
25
was synthesized by using a mechanical alloying (MA) process under an argon gas atmosphere for potential use as a aluminum based engineering material. Microstructural evolution, thermal behaviour, and mechanical properties of the mechanically alloyed powders as a function of milling time were investigated by means of X-ray diffraction (XRD), differential scanning calorimetry, transmittance electron microscopy and scanning electron microscopy (SEM). The XRD and SEM results revealed that the microstructure of the powders materials changed during MA. The crystallite size of Al–B–Mg powders decreased with increasing milling time. The average crystallite size was determined. The results also showed that after 100 h of milling time nanostructured α-Al (Mg, B) solid solution phase whose crystallite sizes are below 17 nm were obtained. Also, radiation shielding parameters have been investigated using NaI (Tl) γ-ray spectrometry at 662 and 1173 keV energies obtained via
137
Cs and
60
Co radioactive point sources. The obtained experimental data have been compared with XCOM theoretical data. The experimental data was utilized to calculate the half-value layer, tenth-value layer, and mean free path values. According to the obtained data, Al
50
Mg
25
B
25
alloy powder prepared and annealed at 300 °C has been shown to provide better protection against radiation.
A nuclear analytical technique, namely instrumental photon activation analysis (IPAA), was used to determine Sr and Ca concentrations in human teeth. This work was conducted using the first ...accelerator facility, an off-shelf clinical linear accelerator (cLINAC), in Turkey. The tooth samples supplied by the Akdeniz University Faculty of Dentistry were analyzed for determination of the Sr/Ca element ratio. The results were obtained to demonstrate the impact of socioeconomic changes on dietary habits. A calibration material (CM; a mixture of calcium and strontium oxides) was required for quantification of the analytical results. The tooth samples, together with the CM, were exposed to 18 MeV end-point energy bremsstrahlung photons from the cLINAC. Thereafter, the γ-ray spectra of the samples and the CM were obtained using high resolution γ spectroscopy. Variations in the Sr/Ca ratio in the teeth of patients fed with beef and fizzy beverages were investigated in this study.
It is very important that the shielding material used in radiation
treatment and imaging centers can effectively protect against radiation and
that this material is cost-effective. Therefore, studies ...are underway on the
development of different types of shielding materials. In this study, radiation
absorption properties of sodium tungstate (Na2WO4) and sodium molybdate
(Na2MoO4) coated wall papers were investigated. The beta radiation absorption
properties of these elements which are applied on wall papers in different
densities (100% precipitated calcium carbonate (PCC), 2.5 g, 5 g, and 7.5 g
amounts of Na2WO4 and Na2MoO4 and various thicknesses (0.172-0.258 mm) were
investigated. The wallpapers were irradiated with 4 MeV-energized electrons and
measurements were taken with the PTW brand electron detector. The linear
absorption coefficients of the wallpapers were obtained and half value layer
(HVL) and one-tenth value layer (TVL) were calculated from these results.
According to the results, it is observed that the beta radiation absorption
properties of these wallpapers increase as the density of Na2WO4 and Na2MoO4
increases and as the coating thickness increases in the coating materials used
to cover the surface of the wallpapers.
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•gCN (graphitic carbon nitride) can be used in many areas such as sensing, biomedical applications, wastewater and environmental treatment•gCN synthesized from different ratios of ...urea and thiourea (0, 25, 50, 75 and 100%) were produced and their radiation shielding properties were investigated via NaI(Tl) (ORTEC® 905-4) detector system.•From obtained radiation shielding results, gCN provides effective results in radiation shielding.
Graphitic Carbon Nitride (gCN) can be used in many fields such as sensing, solar energy and device construction. In this study, gCN obtained from urea and thiourea precursors were produced to determine the radiation shielding properties. The structural features and optical properties of these produced samples were investigated. Also, the radiation shielding properties were determined experimentally. Here, Linear Attenuation Coefficient values were determined experimentally and Mass Attenuation Coefficient, Half-Value Layer, Tenth-Value Layer and Mean Free Path values were calculated employing this value. According to obtained results, it is seen that obtained gCN can be used effectively in radiation shielding.
With the development of technology, the application areas of radiation have expanded and have an important place in our daily life. For this reason, we need more advanced and effective shielding ...materials to protect lives from the harmful effects of radiation. In this study, a simple combustion method was utilized to synthesize zinc oxide (ZnO) nanoparticles, and obtained nanoparticles' structural and morphological features were examined. The synthesized ZnO particles are used to produce different percentages (0, 2.5, 5, 7.5, 10%) of ZnO-doped glass samples. The structural and radiation shielding parameters of obtained glasses are examined. For this purpose, the Linear attenuation coefficient (LAC) has been measured via 65Zn and 60Co gamma sources and NaI(Tl) (ORTEC® 905–4) detector system has been used. Using the obtained LAC values, Mass Attenuation Coefficient (MAC), Half-Value Layer (HVL), Tenth-Value Layers (TVL), and Mean-Free Path (MFP) for glass samples have been calculated. According to these radiation shielding parameters, it was concluded that these ZnO doped glass samples provide effective results in radiation shielding and can be used as a shielding material effectively.
•We provide experimental report for our work on ZnO nanoparticle doped borate glass.•The average diameter of ZnO particles is calculated as 23.69 nm from TEM observation.•The radiation shielding property improved with the increase of the doped ZnO nanoparticle ratio.
We have looked at all past core meltdowns (Three Mile Island, Chernobyl and Fukushima incidents) and postulated the fourth one might be taking place in the future most probably in a newly built ...reactors anywhere of the earth in any type of NPP. The probability of this observation is high considering the nature of the machine and human interaction. Operation experience is a very significant parameter as well as the safety culture of the host nation. The concerns is not just a lack of experience with industry with the new comers, but also the infrastructure and established institutions who will be dealing with the Emergencies. Lack of trained and educated Emergency Response Organizations (ERO) is a major concern. The culture on simple fire drills even makes the difference when a severe condition occurs in the industry. The study assumes the fourth event will be taking place at the Akkuyu NGS and works backwards as required by the “what went wrong ” scenarios and comes up with interesting results. The differences studied in depth to determine the impact to the severe accidents. The all four design have now core catchers. We have looked at the operator errors’like in TMI); Operator errors combined with design deficiencies(like in Chernobyl) and natural disasters( like in Fukushima) and found operator errors to be more probable event on the Akkuyu’s postulated next incident. With respect to experiences of the operators we do not have any data except for long and successful operating history of the Soviet design reactors up until the Chernobyl incident. Since the Akkuyu will be built, own and operated by the Russians we have found no alarming concerns at the moment. At the moment, there is no body be able to operate those units in Turkey. Turkey is planning to build the required manpower during the transition period. The resolution of the observed parameters lies to work and educate, train of the host nation and exercise together.
In recent years, the production of alternative materials instead of lead in the environmentally sensitive and non-toxic material research in radiation shielding has been gained importance. In this ...study, transparent pristine and boron (B) doped zinc oxide (ZnO) thin films were synthesized by spray pyrolysis method. The crystalline structure, morphology and optical properties of the produced films were investigated with X-ray diffractometer (XRD), scanning electron microcopy (SEM) and Uv–vis spectrometer. The wurtzite structure of pure ZnO was deformed by boron doping found from XRD results. The hexagonal rods have been worsened with boron doping observed from SEM analysis. The factors related to radiation shielding; mass and linear attenuation coefficients, half value layer, mean free path and tenth value layer of different percentage (5, 10 and 20%) B doped ZnO thin films were examined. To perform these measurements, PTW® electron detector and irradiation have been utilized with 6 MeV energized electrons by using VARIAN®. The obtained results from these measurements can be useful to understanding of radiation shielding performance of ZnO:B thin films.
•Pristine and boron doped zinc oxide thin films were synthesized by pyrolysis methods.•Optical transmittance of the prepared films were enhanced as a function of boron concentration.•The linear attenuation coefficient increased as the percentage of boron in the thin films increased.•ZnO: B thin films can be used as radiation shielding with different materials in radiation treatment centers.
Reaction cross section knowledge is crucial to application nuclear physics such as medical imaging, radiation shielding and material evaluations. Nuclear reaction codes can be used if the ...experimental data are unavailable or are improbably to be produced because of the experimental trouble. In this study, there action cross sections of some target alkaline earth elements have been calculated by using pre-equilibrium and equilibrium nuclear reaction models for nucleon induced reactions. While these calculations, the Hybrid Model, the Geometry Dependent Hybrid Model, the Full Exciton Model, the Cascade Exciton Model for pre-equilibrium reactions and the Weisskopf-Ewing Model for equilibrium reactions have been used. The calculated cross sections have been discussed and compared with the experimental data taken from Experimental Nuclear Reaction Data library.
The widespread use of nuclear technology has increased interest in the concept of radiation shielding. Therefore, thin films are one of the applications of interest in both science and industry used ...in various applications such as laboratory equipment, optoelectronic materials, and radiation shielding materials. The present work synthesized pure indium oxide (In2O3) and samarium (Sm) doped In2O3 thin films by the spray pyrolysis method. The obtained samples were characterized by X-ray diffractometer, scanning electron microscopy (SEM), and Uv–vis spectrometer. The cubic crystalline form of synthesized In2O3 thin film was observed from the X-ray pattern. By introducing the Sm element, the crystalline peaks of In2O3 gradually decreased with increasing doping concentration. The experimental linear attenuation coefficients (μ) of different percentages (0, 5, 10, and 20%) Sm doped In2O3 thin films have been determined using 6 MeV energized X-ray via VARIAN® and PTW® ion chamber. Accordingly, some terms important in shielding were calculated using μ. The obtained results from these measurements can help understand the radiation shielding performance of In2O3: Sm thin films.
•The impact of (0, 5, 10 and 20%) Sm element on In2O3 thin films have been investigated.•The optical, structural and shielding properties of these thin films have been investigated.•The linear attenuation value increased as the Samarium contribution increased.•Mass attenuation, half and tenth value layer, mean free path values have been obtained.•The effective atomic number and effective electron density have been obtained.
Boron is usable element in many areas such as health, industry and energy. Especially, Boron neutron capture therapy (BNCT) is one of the medical applications. Boron target is irradiated with low ...energy thermal neutrons and at the end of reactions alpha particles occur. After this process recoiling lithium-7 nuclei is composed. In this study, charge particle induced nuclear reactions calculations of Boron target nuclei were investigated in the incident proton and alpha energy range of 5–50 MeV. The excitation functions for 10B target nuclei reactions have been calculated by using PCROSS Programming code. The semi-empirical calculations for (p,α) reactions have been done by using cross section formula with new coefficient obtained by Tel et al. The calculated results were compared with the experimental data from the literature.
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