School of Physical Sciences (SPS)
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Item A comparative study of the radiation dose response of (ZnO)x(TeO2)1-x thin films for high energy X-ray application(ELSEVIER, 2025) M.M. Idris; OLARINOYE, OYELEKE; Kolo, M. T.,; S.O. Ibrahim; U. Rilwanc; M.I. SayyeddThe current research work determines the X-ray radiation effects on the current–voltage (I-V) characteristics of zinc oxide-doped tellurium dioxide thin film as a dosimetric material for X-ray detection and measurement. Five thin-film samples of (ZnO)x(TeO2)1-x (where x =0.0 wt% (D1), 0.2 wt% (D2), 0.4 wt% (D3), 0.6 wt% (D4), and 1.0 wt% (D5)) were prepared with an aqueous solution of zinc acetate dehydrate and tellurium dioxide precursor on a soda-lime glass substrate using the spray pyrolysis technique. XRD study revealed a polycrystalline structure of the films and showed diffraction peaks belonging to paratellurite TeO2 and wurtzite ZnO in all film samples. A peak shift was observed, indicating the presence of ZnO in the TeO2 crystal lattice. FESEM imagery revealed roughness and the film grain size, which decreased when the concentration of ZnO increased. The optical assessment showed superior transparent behavior in the spectrum of visible light and a minor fall in the optical band-gap value when the concentration of ZnO increased. The I-V characteristic obtained for all the thin-film samples showed a linear increase of current as a function of the applied voltages and X-ray doses ranging from 0.0 to 6.0 V and 50–250 cGy, respectively. The I-V characteristic response of the thin-film samples studied were in the order of D3 >D1 >D2 >D4 >D5. The thin films’ dosimetric sensitivity (minimum measurable dose) values were in the range of 0.610–2.180 mAcm2Gy 1 (0.4590–1.6390 mGy) for D1, 0.370–0.940 mAcm2Gy 1 (1.0640–2.7030 mGy) for D2, 0.610–2.280 mAcm2Gy 1 (0.4390–1.6390 mGy) for D3, 0.00200–0.005280 mAcm2Gy 1 (189.3940–357.1430 mGy) for D4, and 0.00040–0.00150 mAcm2Gy 1 (250.0000–666.6670 mGy) for D1. The R2 value (linearity error) of the I-V plots were in the range of 0.879–0.951 (0.0025–0.0057) for D1, 0.966–0.998 (0.0006–0.0025) for D2, 0.869–0.913 (0.0035–0.0065) for D3, 0.860–0.952 (0.000009–0.00005) for D4, and 0.922–0.978 (0.000002–0.000004) for D5. The ZnO-TeO2 thin-film sensor is therefore a candidate material that can be used for miniaturized radiation measuring devices that can be accommodated in smart devices such as smart watches and smart phonesItem 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 radiationItem 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 therapyItem Gamma-radiation insulating performance of AlON-hardened Na2O–Bi2O3–SiO2–BaO–Fe2O3–ZrO2 glasses(Nature, 2025) Alzahrani, J. S., Alrowaili, Z. A.,; OLARINOYE, OYELEKE; Sriwunkum, C., Kebaili, I., & Al-Buriahi, M. S.Aside high radiation cross-section, high mechanical strength is an essential quality for durable and effective glass shields. Many emerging glass shields are brittle with low strength parameters; consequently, limiting their longstanding applications. In this study, the use of AlON (aluminium oxynitride) to increase the hardness of a Zr-based glass system and the consequent effects on the glass density and gamma shielding capacity were investigated. AlON was produced from a combination of AlN and Al2O3 powders through the solid-phase reaction process at 1750 °C. The melt-and-quench process was then used to make the Zr-based (Na2O–Bi2O3–SiO2–BaO–Fe2O3–ZrO2) glass. The glass was homogeneously mixed with varying quantities (0 (GZr8), 4 (GZr8Al4), and 8% (GZr8Al8) by weight) of AlON powder. Using the FLUKA Monte Carlo code, the gamma photon interaction parameters of the AlON-doped glasses were obtained. The density of the glasses increased from 2.90 to 3.11 g/ cm3 as the AlON mass proportion increased from 0 to 8%. For GZr8, GZr8Al4, and GZr8Al8, the mass attenuation coefficient had values in the range 0.0316–38.9421 cm2/g, 0.0315–38.8504 cm2/g, and 0.0311–37.0391 cm2/g, respectively. The range of the half-value layer and mean free path for 0.01515 MeV photons is about 0.01–7.54 cm and 0.01–10.87 cm for GZr8, 0.01–7.19 cm and 0.01–10.38 cm for GZr8Al4, and 0.01–7.14 cm and 0.01–10.31 cm for GZr8Al8. The introduction of AlON into the glass matrix queched photon buildup factors and enhanced the photon shielding ability of the GZr8 glass system. GZr8Al8 can displace many existing shielding materials, including glasses, concrete, and rocks, based on the analysis of the obtained results. Aside high gamma shielding efficiency, the mechanical strength and Pb-free nature are other attractive features that give the AlON-doped glasses an edge over many existing gamma shielding materials. The present glass system is useful for durable gamma ray shielding of small-scale gamma sources gamma sources applied in medicine and radiation research.