Sürdürülebilir Kalkınma Amaçları
Yazarlar
- Güler, Ömer(15)
- ALMisned, Ghada(12)
- Tekin, H.O.(11)
- Taşgın, Yahya(7)
- Baykal, Duygu Sen(6)
- Yayla, Nihal(6)
- Yılmaz, Demet(6)
- Kök, Mediha(5)
- Özkul, İskender(5)
- Alkarrani, Hessa(4)
- Kilic, G.(4)
- Pekdemir, Mustafa Ersin(4)
- Sayyed, M.I.(4)
- Sen Baykal, Duygu(4)
- Askin, A.(3)
- Canbay, Canan Aksu(3)
- Guler, Omer(3)
- Guler, Seval Hale(3)
- Güler, Seval Hale(3)
- Kanca, M. Sait(3)
- Karaduman, Oktay(3)
- Selçuk Pekdemir, Sibel(3)
- Birdogan, Selcuk(2)
- Dogan, Zulfu Murat(2)
- Durmus, Hasan(2)
- Esen, Yuksel(2)
- Ilik, E.(2)
- Kalay, Ece(2)
- Kanca, Muhammed Sait(2)
- Kavaz, E.(2)
- Marimuthu, K.(2)
- Sakar, E.(2)
- Sathiyapriya, G.(2)
- Taşgin, Yahya(2)
- Tekin, Huseyin Ozan(2)
- Agar, O.(1)
- Albayrak, M Gökhan(1)
- Albayrak, M. Gökhan(1)
- Albayrak, M.Gökhan(1)
- Alim, B.(1)
Yayınlar
- MakaleYalnız künye2024Scopus SJRQ1A closer-look on W and Pb alloys: In-depth evaluation in elastic modulus, gamma-ray, and neutron attenuation for critical applications
ALMisned, Ghada; Susoy, Gulfem; Sen Baykal, Duygu; Alkarrani, Hessa; Güler, Ömer; Tekin, H.O.
This investigation assesses the gamma-ray and neutron attenuation properties of various alloys, including Pb90Cu10, A5, Manganin-R, Cu0.2Ag0.8, SA4, and W-based, to uncover efficient and cost-effective radiation shielding materials. Our study centers on alloys featuring elements such as lead, molybdenum, silver, and tungsten, selected for their unique protective qualities against radiation. Employing computational methods to evaluate critical parameters like mass attenuation coefficients, half-value layers, linear attenuation coefficients, and effective atomic numbers, transmission factor, we found the W-based alloy to exhibit exceptional shielding properties, primarily due to its tungsten content. Interestingly, this alloy also demonstrated the highest elastic modulus among the samples studied, indicating a potential synergy between an alloy's mechanical strength and its radiation shielding effectiveness. It can be concluded that alloys with higher elastic moduli not only offer better resistance to radiation-induced deformations, enhancing shielding, but also underscore the need for further research on alloys that balance performance, affordability, and environmental impact. The findings underscore the dual importance of composition and mechanical properties in advancing radiological safety and suggest continued investigation into the sustainability and practicality of effective shielding materials.
AtıfScopus28OpenAlex31
İncele - MakaleAçık Erişim2024Scopus SJRQ2Physical and shielding properties of Er2O3 rare earth oxide compound content on PCL/PEG blend
Taşgin, Yahya; Pekdemir, Mustafa Ersin; Yilmaz, Mücahit; Kanca, Muhammed Sait; Kök, Mediha
Rare earth elements (RRE), due to their unique magnetic, electrical, and optical properties, are an important group of elements demanded in many application areas from machine technology to the health industry. In this study, new composites were obtained by mixing Erbium oxide (Er2O3), one of the rare earth element oxides, into PCL–PEG blend, which is also an important material group, in different ratios. The characteristic functional groups of the obtained polymer blend/Er2O3 nanocomposites were determined by the ATR-IR, and as the erbium oxide ratio increased, characteristic peaks of the polymers in the blend as well as characteristic signals of the Er–O–Er bond were found. When the thermal behavior of the obtained composites was examined, it was observed that the polymer blend exhibited miscible blend properties and the melting temperature of the polymer blend increased as the Er2O3 ratio increased. In addition, it was determined that the thermal stability of the composite increased significantly. X-ray measurements of composites at room temperature support other measurement results. It was determined that the presence of Er-RRE oxide increased the crystal structure feature in the polymer blend composite. Gamma radiation shielding capabilities of polymer materials containing different erbium ratios were investigated by calculating shielding parameters such as half value layer (HVL), radiation protection efficiency (RPE), and mean free path (MFP). Cs-137 and Co-60 radioactive sources were used as gamma sources. According to the obtained measurement results, Erbium oxide increased the absorption property of the polymer composite material. Graphical abstract: [Figure not available: see fulltext.].
AtıfScopus26WoS28OpenAlex29İncele - MakaleAçık Erişim2023Scopus SJRQ1A comprehensive study on structural properties, photon and particle attenuation competence of CoNiFeCr-Ti/Al high entropy alloys (HEAs)
Sakar, Erdem; Guler, Omer; Alım, Bünyamin; Say, Yakup; Dikici, Burak
It is well known that high entropy alloys (HEAs) have a wide range of potential applications as radiation shielding due to their superior properties. The CoNiFeCr-Ti/Al compositions were chosen for their low cost as HEA in this study. The HEAs were successfully produced using the mechanical alloying (MA) method with equimolar CoNiFeCr, CoNiFeCrAl, and CoNiFeCrTi compositions. The production and structural properties of the alloys were investigated in detail. Besides, the photon and particle radiation shielding properties of the HEAs were calculated with the help of Phy-X/PSD, SRIM (10 keV-20 MeV), and ESTAR (10 keV-20 MeV) programs. The photon-matter interaction parameters were calculated in both specific photon energies emitted from 241Am, 133Ba, 109Cd, 60Co, 137Cs, 131I, and 22Na nuclides and a continuous energy range of 15 keV-15 MeV. The characterization of the alloys was investigated by using X-ray diffraction (XRD) and scanning electron microscopes (SEM) attached to an energy dispersive spectroscopy (EDX). It was found that the HEAs have a highly amorphous structure due to the selected production method. The crystal size of the alloys was calculated as 70, 35, and 20 nm for CoNiFeCr, CoNiFeCrAl, and CoNiFeCrTi, respectively. In terms of shielding properties, it has been determined that the produced HEAs have better shielding characteristics for photon and particle radiations than standard shielding concretes. In addition, the results demonstrated that CoNiFeCr alloy, which has the best shielding ability among the HEA alloys, can be used as a shielding material application requiring photon, electron, proton, alpha, and neutron radiations.
AtıfScopus30WoS32OpenAlex32İncele - MakaleYalnız künye2021Scopus SJRQ2Investigation of Microstructural and Mechanical Properties of Different Titanium Alloys for Gamma Radiation Properties and Implant Applications
Taşgın, Yahya
In this study, the advantages and disadvantages of different titanium alloys used as industrial and biomedical implant materials are evaluated within the scope of multiple parameters. This research is supported by simulations and aims to understand how titanium and titanium alloys differ mechanically, micro-structurally and in terms of radioactivity. The matrix material of the eight samples used in this research is titanium. The effects of different elements such as Al, V, Sn, Ni, Pb, Mo, Cr, Zr, Fe, Nb, Co on titanium have been examined, the results are compared by considering multiple parameters, and the superior properties of the prominent alloys are highlighted. As a result of the mechanical and electrical tests performed on the alloys, it is obvious that the titanium alloy consisting of Mo and Nb has the highest Brinell hardness, elastic modulus, tensile strength and electrical conductivity parameters compared to other alloys examined within the scope of this research. In the metallographic studies and analyses on samples made up of different alloys, different structures and images emerge for each alloy. These elements rapidly lower the solidification temperature of the material, allowing the β phase to be formed. It has been observed that the two-phase situation has positive effects on the material. On the other hand, the results of gamma ray attenuation tests reveal that Mo and Nb, which make up the alloy, have superior performance compared to other alloy samples due to their high atomic number. Graphical abstract: [Figure not available: see fulltext.]
AtıfScopus8WoS7OpenAlex11İncele - MakaleYalnız künye2021Scopus SJRQ2Radiation shielding and mechanical properties of Bi2O3–Na2O–TiO2–ZnO–TeO2 glass system
Sayyed, M.I.; Askin, Ali; Zaid, M.H.M.; Olukotun, S.F.; Khandaker, Mayeen Uddin; Tishkevich, Daria I.; Bradley, D.A.
Recently, heavy metal oxides (HMO) based glass systems attracted great attention to the scientific community to be used as an alternative to the conventional lead, lead composites and concrete based materials for protection of harmful radiation. In this work, we report the role of Bi2O3 on the mechanical and radiation shielding properties of Bi2O3–ZnO–TiO2–Na2O–TeO2 glass system as well as its mechanical behaviour. The mechanical properties of the glasses were calculated using Makishima-Mackenzie model and different shielding factors have been calculated using Monte Carlo simulation via Geant4 code and also using Phy-X software. The mechanical properties based on Makishima-Mackenzie model depend on the values of packing density (Vi) and dissociation energy (Gi) of the oxide constituents. The simulated values of the mass attenuation coefficient showed a good agreement between both approaches. The mass attenuation coefficient (MAC) at 0.284 MeV of the glass with 5 mol% of Bi2O3 is equal to 0.2083 cm2/g, at 0.662 MeV its equal to 0.0785 cm2/g, while at 1.33 MeV, its MAC is 0.0501 cm2/g. The transmitted percentage of the photons through the proposed glasses was found to rise with increasing the energy of the photon, while decreasing with rising the thickness of the glass sample. The transmission factor (TF) revealed that the greater the thickness of the glass, the lower the TF, and the better the shield. Also, the radiation protection efficiency of the glasses was enhanced with the addition of the Bi2O3. The glass sample with composition of 15Bi2O3–10ZnO–5TiO2–5Na2O–65TeO2 possesses the highest effective atomic number among the studied compositions and showed the lowest half value layer. From the obtained data, Bi2O3 seems to be a strong candidate for enhancing the gamma radiation attenuation factors in the bismuth-based tellurite glasses.
AtıfScopus77OpenAlex78İncele - MakaleYalnız künye2020Scopus SJRQ1Structural, elastic, optical and γ-ray shielding behavior of Dy3+ ions doped heavy metal incorporated borate glasses
Divina, R.; Sathiyapriya, G.; Marimuthu, K.; Askin, A.; Sayyed, M.I.
The effect of modifier ions in different basis have been analyzed through a new series of heavy metals incorporated borate based glasses 39H3BO3+30PbO+20MO+10Bi2O3 +1Dy2O3 (where M=Ca,Sr,Ba,Na and K) which are synthesized following melt quenching technique for radiation screening applications. The potentiality of glasses to withstand the penetration of fast moving neutrons is checked by various studies. Functional groups are identified through different stretching and bending modes of vibrations within the glass membrane through FTIR spectral analysis. In addition to that, other structural properties like Boron-Boron distance (dB−B), molar volume of oxygen (Vo), Oxygen Packing Density (OPD), optical basicity (Λth) and Bond density (nb) are calculated theoretically. The bonding nature (β) and nephelauxetic ratio (δ) values reveals that the glasses possess more of ionic linkages. The high density value exhibited by the Bismuth lead borate glasses indicates their capability to act as a good shielding material in reactors emitting hazardous radiation. Different moduli of elasticity (E, K, G, σ) values for the present glasses are calculated and the results reveal the enhancement in shielding performances when compared to other existing glasses and a comparative study is made on it. Optical studies are carried out and the absorption of Dy3+ions to different energy levels is observed and optical band gap (Eopt) values of the synthesized glasses are calculated along with the Urbach energy (ΔE) values. Radiation shielding properties of the produced glasses were investigated in terms of the mass attenuation coefficients (µm), transmission fraction (T), half value layer (HVL) and effective atomic number (Zeff) parameters. The results attained in the shielding study indicated that glass specimen with M = Ba exhibits enhanced shielding behavior as Ba owns high atomic number (Z) compared to other elements. Glass specimen with M = Na shows the poorest shielding characteristics due to the low Z of Na.
AtıfScopus117OpenAlex107İncele - MakaleYalnız künye2019Scopus SJRQ2Influence of RE oxides (Eu3+, Sm3+, Nd3+) on gamma radiation shielding properties of lead fluoroborate glasses
Wagh, Akshatha; Sayyed, M.I.; Askin, A.; Özpolat, Özgür Fırat; Sakar, E.; Lakshminarayana, G.; Kamath, Sudha D.
Authors report the change in lead fluoroborate glass properties with change in RE2O3 (RE = Eu, Sm, Nd) chemical composition. The RE2O3 exhibited improvement in the radiation shielding properties of the glass samples. The gamma rays shielding capabilities of the samples were studied using the WinXcom software (for Eu2O3, Sm2O3 doped glasses) and Monte Carlo simulation (for Nd2O3 doped glasses). The results exhibited that the mass attenuation coefficient (μm), effective atomic number (Zeff), and half value layer (HVL) depends on the concentration of RE2O3 and addition of the same significantly increased the shielding capabilities of the glass samples against gamma rays. The increase in photon energy revealed the decrease in radiation shielding properties. The reported density and radiation attenuation properties of RE2O3 doped lead fluoroborate glasses are predominant in radiation shielding applications which will be useful in high strength structures. Of all the glass samples 2.5 mol% of Eu2O3, Sm2O3 and Nd2O3 doped glasses showed enhanced shielding properties.
AtıfScopus40OpenAlex41İncele - MakaleAçık Erişim2019Scopus SJRQ1An investigation on physical, structural and gamma ray shielding features of Dy3+ ions doped Telluroborate glasses
Sathiyapriya, G.; Marimuthu, K.; Sayyed, M.I.; Askin, A.; Agar, O.
Structural, physical and gamma ray shielding properties of Dy3+ doped telluroborate glasses have been discussed. The molar volume of the glasses is proportional to the TeO2 content. The FTIR studies investigate the expansion of TeO2 content and the dynamic change of tetrahedral [BO4] units into trigonal [BO3] units. Using the absorption spectra, optical band gap (Eg) and Urbach's energy (ΔE) values are calculated. The molar volume of oxygen (VO) and boron‑boron separation (<dB–B>) values are increasing while there is a fall in oxygen packing density (OPD) from 0% to 40% of TeO2. The ionic nature of the present glasses is analyzed from the bonding parameter (δ), optical basicity (Λth), covalent and ionic characteristic factors. The gamma photon attenuation investigated employing GEANT4 code. The transmission factor (TF) shows that 0TBD sample (0 wt% of TeO2) has the highest TF, while the 4TBD sample (40 wt% of TeO2) has the lowest TF.
AtıfScopus42İncele - MakaleYayıncıda açık erişim2018Scopus SJRQ1Investigation of usability of limonite aggregate in heavy-weight concrete production
Esen, Yuksel; Dogan, Zulfu Murat
Limonite (Fe2O3.xH(2)O) is a soft or brown, hard iron mineral, usually in yellow colour. It is also used as a pigment since it contains iron ore. It is believed that it can also be used in the production of heavy concrete due to its 60% iron ore content. In this paper, an experimental study was carried out on radiation shielding properties and certain physical and mechanical properties of normal and limonite reinforced concrete. For this purpose, with the normal concretes prepared according to standards, amounts of aggregates were reduced at the rates of 20%, 40%, 60%, 80% and 100% by volume respectively, and heavy concrete mixes were prepared that were obtained by adding limonite at the same rates in their place. With limonite reinforcement, compressive and flexural strength of the concrete produced decreased, water absorption amount increased and their radiation permeability significantly decreased.
AtıfWoS54OpenAlex56İncele - MakaleAçık Erişim2017Scopus SJRQ1Evaluation of physical and mechanical characteristics of siderite concrete to be used as heavy-weight concrete
Esen, Yuksel; Dogan, Zulfu Murat
The objective of this study is to investigate the usability of siderite aggregates mentioned above as a heavy-weight aggregate in the heavy-weight concrete production and their effects on physical properties of the heavy-weight concrete mixture. For this purpose, normal-weight aggregate content was decreased at the rate of 20%, 40%, 60%, 80% and 100% by volume of the concrete mixture prepared and mixtures were prepared by its substitution with siderite aggregate at the same rates. Based on the increase in siderite aggregate in the concrete mixture, a considerable increase in unit weight, compressive strength and tensile strength of concrete was obtained. Plate-shaped concrete specimens obtained from combined normal-weight and heavy-weight aggregates were exposed to radiation with different X-ray source (118 keV, 164 keV) and Co-60 (1250 keV) beam source at cekmece Nuclear Facility. It is clearly seen that the concrete mixture containing siderite aggregate improved 70% radiation absorption characteristics compared to that of the concrete mixture without siderite aggregate. (C) 2017 Elsevier Ltd. All rights reserved.
AtıfWoS53OpenAlex51İncele - MakaleYalnız künye2016Scopus SJRQ1Determination of the effect of lead mine waste aggregate on some concrete properties and radiation shielding
Çullu, Mustafa; Ertas, Haydar
The aim of this study is to determine the radiation absorption capacity of concretes produced from lead mine waste which cannot be processed economically as the lead content is low in the mines they are extracted. Lead mine waste (tallow) were exchanged at ratios of 25%, 50% and 75% respectively with barite and limestone aggregates and samples were prepared at C16, C25 and 05 classes. The compressive strength and the unit weight of the prepared samples were determined. The linear absorption coefficients of prepared concrete samples at 662 keV of energy were determined. In addition the relationship between the radiation absorption capacity and the compressive strength-unit weight was investigated. The experiments demonstrated that best absorption was in concrete samples with 100% barite content (100B). On the other hand in the concrete samples prepared from the mixture of limestone and lead mine waste aggregates, it was observed that radiation absorption capacity decreased due to decreasing amount of barite. In concrete samples prepared from the mixture of lead mine waste and limestone aggregates, it was observed that radiation absorption capacity increased due to increasing amount of mine waste aggregates in the concrete. As a result it was observed that lead mine waste aggregates do not absorb as much radiation as barite aggregates depending on the ratio increase of lead mine waste in the aggregate added to the concrete mixture. However the absorbed radiation amount was observed to be higher compared to limestone aggregates. (C) 2016 Elsevier Ltd. All rights reserved.
AtıfWoS70OpenAlex71İncele