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- MakaleAçık Erişim2024Scopus SJRQ2Titanium alloys: A closer-look at mechanical, gamma-ray, neutron, and transmission properties of different grade alloys through MCNPcode application
ALMisned, Ghada; Guler, Omer; Sen Baykal, Duygu; Kilic, G.; Tekin, H.O.
Titanium alloys play a vital role in optimizing the effectiveness and security of nuclear reactors, strengthening structural durability, and facilitating the effective handling of nuclear waste. The aim of this study is to investigate the gamma-ray, neutron, and transmission properties of four common titanium alloys through the examination of the deposited energy amount in the liquid sodium coolant material, in relation to the mechanical properties of these alloys. MCNP (version 6.3) is utilized for designing the titanium pipes. Next, the pipes were re-designed considering the elemental mass fractions and densities of the investigated titanium alloys. Grade 26 sample is reported with the highest values of mass attenuation coefficients and the lowest HVL values among those investigated alloys. Grade 26 is reported to have the lowest TF value, whereas Grade 12 demonstrated the highest TF value. The highest Effective Removal Cross Section (ΣR, 1/cm) value against fast neutrons is reported for Grade 26. The utilization of Grade 26 sample as pipe material resulted in the lowest deposited energy amount (MeV/g) and subsequent lowest contamination in the coolant material. Out of the alloys that were chosen for analysis, it has been determined that Grade 26 exhibits the highest level of strength. It can be concluded that the Grade 26 alloy exhibits desirable characteristics for applications in nuclear technologies that require superior gamma-ray and neutron absorption properties, as well as exceptional mechanical properties. Nevertheless, it is essential to emphasize the importance for ongoing studies to enhance the existing material properties of Grade 26, with the aim of achieving improved safety and efficacy in nuclear applications.
AtıfScopus11OpenAlex11
İncele - MakaleAçık Erişim2024Scopus SJRQ1Development and in-depth experimental characterization of novel TiZrNbHfTaOx reinforced 316L stainless steel for advanced nuclear applications
Güler, Ömer; Albayrak, M. Gökhan; Başgöz, Öyküm; Kavaz, E.; Alkarrani, Hessa; ALMisned, Ghada; Tekin, H.O.
Oxide Dispersion Strengthened (ODS) materials are known for their exceptional performance in high-temperature and radiation environments. This study explores the radiation shielding properties of 316L Stainless Steel reinforced with TiZrNbHfTaOx High-Entropy Oxide (HEO). By integrating HEOs into the 316L stainless steel matrix, we aim to enhance its structural and radiation shielding properties. The HEO was synthesized using high-energy ball milling and oxidation processes, followed by thorough characterization using X-ray diffraction (XRD), scanning electron microscopy (SEM), and energy-dispersive spectroscopy (EDS). Our results indicate significant improvements in both gamma-ray and neutron shielding properties. The 316L SS samples reinforced with 20 % HEO exhibited the highest mass attenuation coefficients (MAC), lowest half-value layers (HVL), and highest effective atomic numbers (Zeff) across all tested photon energies. These enhancements are attributed to the high atomic number elements and unique synergistic effects of HEOs. Neutron shielding was evaluated through equivalent dose rate measurements, with the 20 % HEO sample demonstrating the highest absorbed dose rate percentage and superior neutron interaction cross-sections. Benchmarking against standard materials confirmed the superior performance of HEO-reinforced 316L SS, making it a promising candidate for advanced radiation shielding in nuclear reactors and other high-radiation environments. Our findings suggest that HEO reinforcement not only improves mechanical properties but also significantly enhances the radiation protection capabilities of 316L stainless steel.
AtıfScopus12OpenAlex13İncele - Yüksek Lisans TeziAçık Erişim2022Nadir toprak elementleriyle katkılandırılmış borat camların fiziksel ve radyasyon zırhlama özelliklerinin incelenmesi
İlyas İzgüden
Bu çalışmada Ülkemizde yer alan zengin bor madeni rezervinin daha verimli kullanılması amacıyla ana maddesi bor oksit olan ve içerisine yine ülkemizde ham madde olarak bulunan ve yeni keşifler ve incelemelere konu nadir toprak elementleri katkılanarak hazırlanan ve kurşun katkılı camlara alternatif olabilecek ve yüksek teknoloji ürünlerinde (Akıllı cihaz ekranları, uzay ve sağlık teknolojileri gibi) kullanılabilecek yeni nesil radyasyon kalkanlayıcı camlar üretmektir. Üretimi yapılan ürünlerin öncelikle XRD yöntemi ile faz tanımlaması yapılmış ve numunelerin amorf yapısına sahip cam olduğu belirlenmiştir. Üretilen numunelerin FTIR yöntemi ile kimyasal bağları ve moleküler yapıları araştırılarak düzgün bağlar oluşturan camlar olduğu belirlenmiştir. Elde edilen numunelerin UV-Vis Spektroskopisi yöntemi ile ışık geçirgenliği ve soğurma spektrumları belirlenerek normal cam karakteri gösterdiği belirlenmiştir. Camların camsı özelliklerinin iyi sonuçlar verdiği tespit edilmiş ve mekanik özelliklerden yoğunluk, sertlik, kırılma toklukları ve gevreklikleri incelenmiş ve sonuçları değerlendirilmiştir. Cam örneklerinin radyasyon zırhlama ölçümleri Atatürk Üniversitesi Fen Fakültesi Fizik Bölümü Prof. Dr. Wolf Weyrich Yüksek Enerji Spektroskopisi Laboratuvarı'nda bulunan deney düzeneği kullanılarak yapılmış ve cam örneklerinin kurşun katkılı camlara alternatif olabilecek seviyede radyasyon kalkanlama yaptığı belirlenmiştir. Bu çalışmanın amacı yapılan nadir toprak elementleri katkılı borat camlarda radyasyon zırhlamanın yanı sıra mekanik ve fiziksel özelliklerinin iyileştirilmesinde yardımcı olacak bir yayın (Tez) oluşturarak bilimsel çözümler sunmaktır.
- MakaleYalnız künye2020Scopus SJRQ1Linear, nonlinear optical and photon attenuation properties of La3+ doped tellurite glasses
Boukhris, Imed; Kebaili, Imen; Sayyed, M.I.; Askin, A.; Rammah, Y.S.
Linear and nonlinear optical features of La3+ doped tellurite glasses in the form 75TeO2–10ZnO –5Li2O –(10-x)Nb2O5 –xLa2O3: x = 0, 0.5, 1.0, 1.5, 2.0, and 2.5 in mol% (abbreviated as La0.0. La0.5, La1.0, La1.5, La2.0, and La2.5) were investigated. Also, the γ-photons attenuation parameters were tested utilizing Geant4 simulation code. Results revealed that the molar polarizability (αmolar) takes values from 8.685 × 10−24 to 7.933 × 10−24 cm3, while the molar refraction (Rmolar) changes from 21.886 to 20.219 (cm3/mol) for La0.0 to La2.5 glasses. The static dielectric constant (εstatic) varies from 6.368 to 5.191, whereas optical electronegativity (χ*) varies from 0.690 to 0.852 for La0.0-La2.5 glasses. Non-linear optical susceptibility (χ3) decreases from 5.675 × 10−12 to 2.109 × 10−12 (esu) with increment La2O3 content in the glasses, while non-linear refractive index (n2optical) decreases from 8.472 × 10−11 to 3.488 × 10−11 (esu). The radiation attenuation characteristics for the tested glasses were investigated with the help of Geant4 code. The mass attenuation coefficient (μm) was simulated between 0.284 and 2.506 MeV. The influnce of La2O3 on the shielding parameters was examined. Among the studied glasses, La2.5 posseses the highest μm values. Also, La2.5 sample has the lowest transmission fraction, which implies that more photons can be attenuated with La2.5 glass using a thin glass layer. From the transmission fraction results, we found that thick glasses are needed to attenuate gamma rays coming at high energies. At 0.511 MeV, the half value layer (HVL) value of the La0.0 glass is 1.49 cm while, at the same energy, the HVL value of the La2.5 glass is 1.44 cm.
AtıfScopus34OpenAlex35İncele