School of Physical Sciences (SPS)
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School of Physical Sciences (SPS)
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Item Factors Influencing Patient Dose in Diagnostic Radiography.(SET, 2008) OLARINOYE, OYELEKE; Igwe, KItem 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.Item B2O3/PbO/Na2O/MgO/Nb2O5 glasses: fabrication, physical, optical characteristics as well as photons/neutrons/beta particles attenuation capacities.(ELSEVIER, 2022) Alsaif, N. A., Rammah, Y. S.,; OLARINOYE, OYELEKE; Ahmed, E. M., & Abouhaswa, A. S.Physical, optical characteristics, and radiation attenuation capacities of the prepared (50-x) B2O3 + 30PbO + 10Na2O + 10MgO + xNb2O5 glasses with various doping ratios x = 0, 2, 4, 6, and 8 mol% have been investigated. Glasses were prepared using the well-known melt quenching process and named as their corresponding x value. The density and molar volume of the prepared glasses were increased from 4.71 g/cm3 and 23.76 cm3/mol for the sample with free Nb2O5 to 4.91 g/cm3 and 25.99 cm3/mol for the rich sample with x = 8 mol% of Nb2O5. With increasing Nb2O5 concentration, the broad near-visible band centered was moved towards higher wavelength. The direct band gap energies of glass samples felt from 3.728 to 2.939 eV, while the indirect band gap energies from 3.032 to 1.822 eV as the Nb2O5 substitution ratio increased. Urbach’s energies of the prepared samples were increased with the increasing of Nb2O5. For photons, the maximum values of mass attenuation coefficient (MAC) were 32.67, 33.02, 33.38, 33.74, and 34.10 cm2/g for x = 0 – x = 8, respectively at 0.015 MeV, while the least corresponding MAC value of 0.0286, 0.0288, 0.0291, 0.0293, and 0.0295 cm2/g was obtained at 10 MeV. For neutrons, the fast (MAC)FN was decreased from 0.0185 – 0.0161 cm2/g, while the thermal (MAC)TN was decayed from 6.6538 – 5.5903 cm2/g. Analysis of the TSP and CSDA range of the glasses emphasize the fact that there is no significant difference in the charged particle of the glasses irrespective of the weight fraction of Nb2O5 relative B2O3. Results confirm that the current glasses are superior for radiation shielding materials compared to some commercial concrete and glasses.Item Comparison of radiation shielding and elastic properties of germinate tellurite glasses with the addition of Ga2O3.(ELSEVIER, 2022) Alfryyan, N., Alrowaili, Z. A., Somaily, H. H.,; OLARINOYE, OYELEKE; Alwadai, N., Mutuwong, C., & Al-Buriahi, M. S.Thecurrent researchelucidatesthenuclearshieldingcapacityofgerminatetelluriteglasses: 41.7GeO2–41.7TeO2–16.6Ga2O3,37.5GeO2–62.5TeO2,10.4GeO2–72.9TeO2–16.7Ga2O3and12.5 GeO–87.5TeO2. Gamma-ray photon, fast neutron and electron shielding parameters of the present glassy materials were evaluated and studied via the Geant4Monte Carlo, Phy-X/PSD software, ESTAR and analytic computations. In addition, Makishima–Mackenzie’s theory was applied to assess the elastic properties of the studied tellurite glass systemcontainingGa2O3 and/or GeO2. The effective atomic number of the glasses varies from19.14to44.08for41.7GeO2–41.7TeO2–16.6Ga2O3,20.63–48.02for37.5GeO2–62.5TeO2, 21.15–48.15 for 10.4GeO2–72.9TeO2–16.7Ga2O3 and 22.42–50.29 for 12.5GeO2–87.5TeO2. The obtained fast neutron removal cross sections of the glasses were 0.0991, 0.0966, 0.1024and0.1021cm−1,respectively,for41.7GeO2–41.7TeO2–16.6Ga2O3,37.5GeO2–62.5TeO2, 10.4GeO2–72.9TeO2–16.7Ga2O3 and 12.5GeO2–87.5TeO2. Also, an equilibrium is reached between total stoppingpower (TSP)due to radiation and collision for electron sate nergy =1.0MeVwherethe TSPwasminimumin theinvestigated glasses. Computed Young’s modulus for37.5GeO2–62.5TeO2wasthelowestwithavalueof0.218GPawhiletheother three glasssampleshavealmostequalvalueof0.226GPa.Thepresentglasses’shieldingabilityout classedsomeconventionalshields,hencehavepotentialforradiationsafety/shieldingpurposes innuclearfacilitiesItem Investigation of Er3+ ions reinforced zinc-phosphate glasses for ionizing radiation shielding applications.(MDPI, 2021) Zakaly, H. M., Ene, A.,; OLARINOYE, OYELEKE; Marzouk, S. Y., Abdel-Hafez, S. H., Shams, M. S., & Rammah, Y. S.Melt quenching technique is used for preparing glasses with chemical formula (70P2O5) (16 x)CdO–(14ZnO)–(xEr2O3), (x = 1–6 mol%). These glasses were named Er1, Er2, Er3, Er4, Er5, and Er6, respectively. Photon buildup factors, fast neutron absorption, and electron stopping of the prepared glasses were examined. Glasses’ density was varied from 3.390 0.003 for the Er1 glass sample to 3.412 0.003 for the Er6 glass sample. The Buildup factor (BUF) spectra have relatively higher values in the Compton Scattering (CS) dominated areas compared to both Photoelectric effect (PE), and Pair Production (PP) dominated energy regions. The highest BUF appeared at the Er atom K-absorption edge, whose intensity increases as the molar concentration of Er2O3 in the glasses increases. The photon absorption efficiency (PAE) of the glasses increases according to the trend (PAE)Er1 < (PAE)Er2 < (PAE)Er3 < (PAE)Er4 < (PAE)Er5 < (PAE)Er6. Fast neutron removal cross-section, FNRC( )values ftheglassesobtainedviacalculation varied from 0.1045–0.1039 cm 1 for Er1–Er6. Furthermore, the continuous slowing down approximation mode (CSDA) range enhances the kinetic energy of electrons for all glasses. Generally, results revealed that the investigated glasses could be applied for radiation shielding and dosimetric media.Item Ge20Se80-xBix (x £ 12) chalcogenide glasses for infrared and gamma sensing applications: structural, optical and gamma attenuation aspect(SPRINGER, 2021) Kebaili, I., Znaidia, S., Alzahrani, J. S., Alothman, M. A., Boukhris, I.,; OLARINOYE, OYELEKE; Al-Buriahi, M. S.This research work represents the impact of adding bismuth on structural and optical properties of Ge20Se80-xBix (0\x\12) chalcogenide glasses. The fundamental experimental measurements are used to evaluate several structural and optical parameters such as the density, molar volume, excess volume, optical bandgap, free volume percentage, the compactness, and packing factor. The results show that as the bismuth content increased from 0 to 12 at. %, the compactness, the optical bandgap, and packing density decreased, whereas the density, molar volume, excess volume and free volume percentage increased. Additionally, Monte Carlo technique is employed to estimate gamma-ray attenuation ability (GAA) of the Ge20Se80-xBix (0\x\12) chalcogenide glasses. The GAA initially decreases with energy for energies up to 6 meV and then increases throughout the remaining part of the energy spectrum. The highest half value layer was obtained at energy of 6 meV with values equal to 4.544, 4.185, 4.029, 3.886, 3.754, 3.631 cm for x = 0, 4, 6, 8, 10 and 12, respectively. Comparatively, the samples with x = 10 and x = 12 possess superior photon shielding properties compared to the other materials except AFZT5. TItem Estimation of Soil-To-Plant Transfer Factors For 238U, 232Th, 40K and 137Cs Radionuclides For Some Selected Medicinal Plants in Some Part of Minna And Kaduna, Nigeria.(2021) Adeleke, F. E.,; OLARINOYE, OYELEKE; Idris, M. M., & Isah, K. U.This study was carried out in some part of Minna (River basin (9.66667oN, 6.55000oE) and Mekunkele (9.5836oN, 6.5463oE)) and Kaduna (Mando (10.590030oN, 7.430019oE) and Kachia (9.8734oN, 7.9552oE)) were Moringa leave, Goat weed, Ginger, and Turmeric are mostly grown in Northern Nigeria. Eleven samples of the medicinal plants comprising of three samples each of Moringa leave, Goat weed, Ginger and two sample of Turmeric, and eleven soil samples of corresponding area where the medicinal plant are grown, were analysed for activity concentrations of natural and artificial radionuclides using HPGe gamma spectrometry. The average annual committed effective dose (AACED) due to the ingestion of radionuclides from medicinal plants were also estimated. The Annual effective dose equivalent (AEDE) for soil sample radiological assessment was estimated. The activity concentrations 238U, 232Th, and 40K were found to vary in the range of 9.512 to 58.984 Bqkg-1, 17.852 to 71.972 Bq kg-1, and 309.836 to 729.451 Bqkg-1, respectively, in the soil samples and 1.343 to 10.367 Bqkg-1, 5.215 to 13.752 Bq Kg-1, and 11.700 to 239.765 Bq kg-1, respectively, in the medicinal plants corresponding to the soil samples. The activity concentration of artificially produced radionuclide 137Cs was BDL to 0.062 Bqkg-1 in the soil and it was below detectable level (BDL) in all the plant samples. The soil to plant transfer factors (TF) varied from 0.330 to 1.089 Bq Kg-1, 0.067 to 0.762 Bq Kg-1 and 0.0740 to 0.318 Bq kg-1, respectively, for 238U, 232Th, and 40K. The AACED due to the ingestion of radionuclides from the medicinal plants varied from 0.0107 to 0.0542 mSvy-1. The AEDE estimated for soil samples vary between 0.0358 to 0.1279 mSv y-1. The reported AACED and AEDE values in this study are much below the world average value of 0.30 mSv y-1 and ICRP recommended safe limit of 1mSv y-1 for an individual respectively. This indicates that it is safe to use these plants for medicinal purposes as there is no radiological health risk attached to the plant and members of the public. This study may also contribute data on local medicinal plants to formulate regulations related to radiological healthcare.
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