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1
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Gamma Attenuation Properties of Some Aluminum Alloys

100%
Yıldırım S., Tugrul A., Buyuk B., Demir E.
Acta Physica Polonica A
|
2016
|
vol. 129
|
issue 4
813-815
EN
In the present work, several commonly used aluminum alloys were investigated for their protective properties against gamma radiation. The gamma transmission technique was used to study the gamma attenuation behavior of the alloys. Cs-137 (0.662 MeV) and Co-60 (1.25 MeV) gamma radioisotope sources, which have relatively medium and high gamma energy levels, were used as gamma sources. The linear and mass attenuation coefficients of the aluminum alloys were measured. The mass attenuation coefficients of the samples were compared with the theoretical values which were calculated using XCOM computer code. The difference between the experimental and theoretical values was below 5%. In addition half-value layer (HVL) values for the studied aluminum alloys were calculated using the linear attenuation coefficients. The attenuation coefficients of the different aluminum alloys were compared. The biggest HVL was observed for 1050 alloy, for both gamma isotope sources, which means the smallest gamma attenuation capability among the studied alloys. It is concluded that the alloys were applicable for the gamma radiation shielding applications.
2
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Comparison of Radiation Properties of Tungsten and Additive Metal Coatings on 321 Stainless Steel Substrate

76%
Demir E., Karabas M., Sonmez S., Tugrul A., Ovecoglu M., Buyuk B.
Acta Physica Polonica A
|
2017
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vol. 131
|
issue 1
71-73
EN
In the present work, the gamma and neutron attenuation behaviors of tungsten, tungsten copper, and tungsten boron-carbide coatings on 321 stainless steel substrate were investigated against Cs-137 and Co-60 gamma radioisotopes and Pu-Be neutron source. The experimental results were compared and evaluated with pure 321 stainless steel to obtain gamma and neutron shielding properties of the coating materials. Tungsten, tungsten copper, and tungsten boron-carbide coatings on 321 stainless steel substrate were fabricated by atmospheric plasma spraying technique. Gamma and neutron transmission technique were used in this study to investigate the radiation behaviors of the coated materials. Linear attenuation coefficients of coated samples were carried out for Pu-Be neutron source. Transmittance values for each specimen were calculated at 0.662 MeV and 1.25 MeV gamma energies. The experimental results were evaluated for radiation shielding properties of the coated samples against gamma and neutron source with pure 321 stainless steel.
3
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Investigation of Natural Radioactivity of Surface Soil Samples in the Vicinity of Edirne-Turkey

76%
Zaim N., Tugrul A., Atlas H., Buyuk B., Demir E., Baydogan N., Altınsoy N.
Acta Physica Polonica A
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2016
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vol. 130
|
issue 1
64-67
EN
The study was carried out to determine radioactivity concentrations in surface soil samples of the city of Edirne in connection with the potential radiological hazards due to Chernobyl event. The natural radionuclide ((226)Ra, (232)Th and (40)K) contents were determined for nine different locations in nine different towns of the Edirne city. Radiation levels were measured. Natural beta-ray activity was also determined for the same locations. The average estimated activity values were determined and compared with reported values for other cities in Turkey and also for many countries of the world. The studied areas do not pose radiological risks to the inhabitants due to harmful effects of the ionizing radiation from the natural radioactivity of the soil.
4
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An Investigation on the Mass Attenuation Coefficients of W-VC-C and W-VC-TiC-C Composites for Gamma Radioisotopes

76%
Tuğrul A., Demir E., Yılmaz O., Sönmez S., Öveçoğlu M., Büyük B.
Acta Physica Polonica A
|
2016
|
vol. 129
|
issue 4
724-727
EN
In this study, tungsten-vanadium carbide-graphite and tungsten-vanadium carbide-titanium carbide-graphite composites (W-VC-TiC-C) which can be used in high-tech equipment were investigated against different gamma radioisotopes. The composite materials were produced via mechanical alloying method in two groups; one of them includes 93% tungsten (W), 6% vanadium carbide (VC) and 1% graphite (C) which was synthesized during three different alloying times (6, 12, 24 hours). Other group of the samples were composited as 91% tungsten, 6% vanadium carbide (VC), 2% titanium carbide (TiC) and 1% graphite (C) which has also three different alloying times (6, 12, 24 hours). Gamma transmission technique was used in the experiments to investigate the gamma attenuation properties of the composite materials. Linear and mass attenuation coefficients of the samples were determined in the experiments and theoretical mass attenuation coefficients were calculated using widely acknowledged XCOM computer code. The experimental mass attenuation coefficients and calculated theoretical results were compared and evaluated with each other. Results showed that gamma attenuation coefficients of the composite materials dependent on alloying time. It can be concluded that increasing the tungsten ratio causes higher linear attenuation coefficient which decreases with increasing gamma energies.
5
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Assessment on Gamma Attenuation Behavior of W-VC-C and W-VC-TiC-C Composites for Co-60 Radioisotope

76%
Demir E., Tugrul A., Sonmez S., Ovecoglu L., Buyuk B., Yilmaz O.
Acta Physica Polonica A
|
2017
|
vol. 132
|
issue 3
830-832
EN
In this study, tungsten-vanadium carbide-graphite (W-VC-C) and tungsten-vanadium carbide-titanium carbide-graphite composite (W-VC-TiC-C) materials were investigated against Co-60 gamma radioisotope. The composite materials which are used in advanced technological studies and high temperature applications in many various fields especially in the areas of fission and fusion armor materials were produced by mechanical alloying method as in two groups. One of them include 93% tungsten (W), 6% vanadium carbide (VC) and 1% graphite (C) also which has three different alloying times (6-12-24 h). Other group of the samples was composed of 91% tungsten, 6% vanadium carbide (VC), 2% titanium carbide (TiC) and 1% graphite (C) also which has three different alloying times (6-12-24 h) and sintered at 1750°C. Co-60 gamma radioisotope source and gamma transmission technique were used in the experiments to investigate the properties of the composite materials. The mass attenuation coefficients of the samples were determined by using experimental results and theoretical mass attenuation coefficients were calculated from XCOM computer code. It can be concluded that increasing the tungsten ratio causes higher mass attenuation coefficient and the composite materials have provided us benefits better than lead for radiation gamma shielding.
6
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Kinetic and Thermodynamic Behavior of Selenium on Modified Bentonite and Activated Carbon using Radiotracer Technique

64%
Tuğrul B., Erentürk S., Haciyakupoğlu S., Karatepe N., Altinsoy N., Baydoğan N., Baytaş F., Büyük B., Demir E., Gedik S.
Acta Physica Polonica A
|
2015
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vol. 128
|
issue 2B
B-180-B-181
EN
This study was aimed to determine kinetic and thermodynamic behaviors of selenium on modified bentonite and activated carbon. Thermodynamic parameters such as enthalpy ΔH, free energy change ΔG and entropy change ΔS of selenium adsorption suggested that the adsorption of Se(IV) on activated carbon and organic-inorganic modified bentonite was exothermic and endothermic process, respectively. The experimental data fitted very well the pseudo-second-order kinetic model for both adsorbents.
7
Content available remote

Investigation for Remediation of Selenium Aqueous Environment with Using Organic Pillared Bentonite by Radiotracer Technique

52%
Tugrul A., Haciyakupoglu S., Erenturk S., Karatepe N., Baytas F., Baydogan N., Altinsoy N., Buyuk B., Orucoglu E., Demir E., Camtakan Z., Okka M.
Acta Physica Polonica A
|
2015
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vol. 127
|
issue 4
1186-1188
EN
In this study remediation of selenium ions from aqueous solutions was investigated using organic pillared bentonite as an adsorbent. Organic pillared bentonite was produced from Resadiye (Tokat, Turkey) bentonite using hexadecylpyridinium chloride and aluminum polyoxy-cations. All the experiments were carried out by tracing with selenium radioisotope. For the production of the radioactive selenium radioisotope, selenium dioxide was irradiated in the central thimble of ITU TRIGA Mark II Training and Research Reactor at Energy Institute of Istanbul Technical University. Radioactivity measurements carried out by the gamma-ray spectroscopy system were used to determine of selenium isotope. The relative importance of test parameters like concentration of adsorbate, pH of the solution and contact time on adsorption performance of organic pillared bentonite for selenium ion was studied. Evaluation of experiments for different parameters showed possibility of remediation of selenium from aqueous media by using organic pillared bentonite.
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