Browsing by Author "Al-Buriahi, M. S.,"

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Apatite-wollastonite glass-ceramics containing B2O3 and Na2O: Potential bioactive material for tissue protection during radiation therapy procedures
(ELSEVIER, 2025) Al-Buriahi, M. S.,; OLARINOYE, OYELEKE; İbrahimoğlu, E.
In this study, an attempt to expand available data and functionality of apatite-wollastonite glass ceramics (AW GCs) in medical therapy and bone engineering by estimating and analysing the physical, structural, fast neutron and gamma interaction properties of B2O and Na2O doped AW GCs is presented. The pristine (AW) and (20 wt% B2O3 and 30 wt% Na2O) doped AW GC (AW-B20-N30) samples were prepared using the cold isostatic press method. The samples were subject of structural and physical characterisation through experimental procedures, while their radiation interaction parameters were obtained following standard theoretical models. Samples’ densities were calculated as 2.917 and 2.613 g/cm3, while the Vickers hardness was 553 and 518 HV for AW and AW-B20-N3, respectively. The structure of the samples revealed that Na2O formed the brianite phase inserted in the apatite structure. The mass and linear attenuation coefficients fluctuated within the ranges, 0.0232-13.6853 cm2/g and 0.0676-39.92 cm-1 for AW and 0.021-8.313 cm2/g and 0.055-21.7223 cm-1 for AW-B20-N30, respectively. The half- and tent-value layers increased from about 0.02 to 10.25 cm and 0.06 to 34.05 cm for AW; for AW-B20-N30, the increase is from 0.032 to 12.61 cm and 0.11 to 41.88 cm, respectively. AW was more effective for shielding photons and fast neutrons, and had lower gamma buildup factors compared to AW-B20- N30. The study showed doping AW with B2O and Na2O could be optimised to get equivalent bone material in radiation studies. The AW GCs also showed better shielding effectiveness compared to some traditional shields and could therefore be applied for shielding tissues outside the target volume in radiation therapy
Dense and environment friendly bismuth barium telluroborate glasses for nuclear protection applications.
(ELSEVIER, 2021) Al-Buriahi, M. S.,; OLARINOYE, OYELEKE; Alomairy, S., Kebaili, I., Kaya, R., Arslan, H., & Tonguc, B. T.
In this paper, four samples of bismuth barium telluroborate glasses in the chemical composition of 20Bi2O3 + 30BaO +xEr2O3 +(30 – x)B2O3 +20TeO2, here x is between 0.05 and 2 mol%) coded as BTBE1, BTBE2, BTBE3, and BTBE4 are reported for potential use in nuclear shielding applications. Geant4 simulations were well designed to obtain the mass attenuation coefficient, μ/ρ for the BTBE1 – BTBE4 specimens at 356 keV–2.51 MeV photon energies. Then, the obtained results are confirmed by using WinXCOM platform. The μ/ρ values were used to assess the nuclear shielding capacity of BTBE1 – BTBE4 specimens in terms of effective atomic number, Zeff, mean free path, MFP, and half-value layer, HVL. Additionally, the buildup factors of BTBE1 – BTBE4 specimens were computed via G-P fitting method at 0.015–15 MeV photon energies and up to 40 mfp (penetration depths). Also, the neutron shielding capacity of the glasses was assessed by calculating the removal cross sections (∑ R). Our results indicate that there is a remarkable enhancement in the gamma shielding features by adding Er2O3 content in the BTBE1 – BTBE4 specimens. It is found that BTBE4 and BTBE3 glass specimens have high shielding quality against nuclear radiation. Gamma-rays and fast neutrons shielding parameters of the BTBE1 – BTBE4 specimens are compared with several commercial and traditional shielding materials. These comparisons concluded that the reported glasses are quite useful for radiation protection purposes.
Evaluation of the structural and radiation transmission parameters of recycled borosilicate waste glass system: An effective material for nuclear shielding.
(2025) Al-Buriahi, M. S.,; OLARINOYE, OYELEKE; Yılmaz, E., Çalıskan, F., & Sriwunkum, C.
In the present study, the influence of B2O3 on the mechanical, physical, and radiation-response characteristics of waste borosilicate glass (BSG) is investigated. Four batches of the glass composite containing 0, 40, 50, and 60 wt % of B2O3 each were prepared and labelled as BB0, BB40, BB50, and BB60, respectively, using the popular melt- quench method. Through a series of experimental processes, the glasses’ density, hardness, and fracture toughness were measured. The mass attenuation coefficients (MACs), neutron removal cross-sections, and stopping powers of ions in the glasses were estimated using a mixture of Monte Carlo simulations and established theoretical models. By adding boron oxide to the WBSG (BB), a 39.50 % and 38.65 % increase in the density of the glass were observed for BB50 and BB60, respectively. About 9 % improvement was achieved in the hardness of the WBSG reinforced with B2O3. The MAC values were between the ranges of 0.0204–5.4610 cm2/g, 0.193–3.8959 cm2/g, 0.0189–3.4421 cm2/g, and 0.0186–3.0347 cm2/g for BB, BB40, BB50, and BB60, respectively, for gamma photons having energies within 0.015–15 MeV range. Also, the half-value layers for the same gamma photons energy range fell within the ranges of 0.053–14.19, 0.064–12.747, 0.061–10.98, and 0.07–11.226 cm for BB, BB40, BB50, and BB60, respectively. The increase in the boron oxide content in WBSG reduced the effective atomic number of the glass. The present glasses offer cheap and effective alternatives as gamma radiation protection barriers to some recently developed and commercial shielding glasses. The inves tigated glasses are recommended as cheap, strong, and effective attenuators for gamma, fast neutron, and light and heavy ion radiation