Physics
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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 A comprehensive investigation on the role of PbO in the structural and radiation shielding attribute of P2O5 – CaO – Na2O – K2O – PbO glass system.(SPRINGER, 2021) Al-Harbi, N., Sayyed, M. I., Kumar, A., Mahmoud, K. A.,; OLARINOYE, OYELEKE; Alhuthali, A. M., & Al-HadeethiThis study presents the synthesis, physical, structural and gamma-ray shielding characteristics of 40P2O5–20CaO–(30-x)Na2O-10K2O–xPbO (x = 0, 5, 10, 15, 20 mol%) glasses. The glass samples coded as PbCKNP1, PbCKNP2, PbCKNP3, PbCKNP4, and PbCKNP5 were prepared using the melt quench method. Na2O substitution by PbO influenced the molar volume and mass density of the glasses. Structural analysis of the glasses using the X-ray diffraction (XRD) and Fourier transform infrared (FTIR) spectroscopy confirmed amorphous structure. The photon shielding parameters of the glasses examined via the Monte Carlo simulation code (MCNP-5) revealed that the glasses’ shielding ability improved as PbO content increased. The highest simulated linear attenuation coefficient (LAC) achieved at 0.015 MeV increased from 21.46 to 159.07 cm-1 as the PbO concentration increased from 0 and 20 mol%. The LAC for all fabricated glass samples showed an exponential reduction trend with gamma photon energy. Based on the simulated LAC values, calculated mass attenuation coefficient (MAC), half-value layer (HVL), transmission factor (TF), and radiation shielding capacity (RSC), PbCKNP5 possessed the best gamma-ray protection ability among the investigated glasses.Item A Study of Chemically Deposited Barium Titanate (Batio3) Thin Films Doped with Natural Dyes and Their Photovoltaic Applications.(International Journal of Scientific Research in Physics and Applied Sciences, 2023-12) Eze, C. N.; A.I. Onyia; M.N. NnabuchiAbstract - Ternary thin films of BaTiO3 nanostructures were synthesized at 90 0C via the Chemical Bath Deposition (CBD) route under room temperature. They were doped with three natural (local/organic) dyes extracted from Lawsonia inermis leaves, Beta vulgaries roots, and Jatropha curcas leaves and thereafter annealed at 400 0C. doped and as-deposited nanostructures were studied employing XRD, SEM, FTIR, UV VIS, and EDXRF. Our X-ray diffraction (XRD) studies revealed a polycrystalline structure. The SEM studies exhibited porous structures advantageous for dye loading. The EDXRF shows the compositional elements. The FTIR reveals the carboxylate and photo physical properties of the dyes. The UV-VIS investigation presented band gap energies Eg of the doped as ad (BR) = 2.60 eV; bd (OO) = 1.61 eV; ccd (LL) = 1.90 eV against the as-deposited AD (g1) = 3.10 eV showing that the dyes reduced the Eg of the thin films occurring from an increased absorption coefficient α. The Nano porous, as-deposited thin films adsorb the extracted dyes on the surface and the interaction between the Nano porous films and the natural dyes used to dope BaTiO3 was studied using UV-VIS spectrophotometer with the aim of investigating their photovoltaic applicationsItem ANALYSIS OF NUCLEAR POWER GENERATION AND MANAGEMENT IN NIGERIA(The Nigerian Journal of Research and Production, 2011-04) Eze, C. N.Abstract Energy is the biggest challenge of the twenty-first century. We must lift much of the world out of poverty, which will require large increases in energy production while simultaneously curbing greenhouse gas emissions. In order to accomplish this, we must adopt solutions that are based on efficiency, renewable, nuclear energy production and safety, and if it can be demonstrated, carbon sequestration and then adopt the idea which said that “an energy future without a significant contribution from nuclear energy simply isn't an option”. Since renewables are by their very nature intermittent, they cannot have a huge impact unless--and until--we develop adequate energy storage technologies and drastically improve our fragile electricity distribution network. In a developing country like Nigeria where energy demand is far more than the supply due to insufficient power generation, incessant outage of power as a result of failure of power generation plants, due to technical faults and ageing, the use of nuclear power plant provides answers to the problems of electricity generation. Since energy is important for socio-economic development considering safety, economy, reliability, sustainability and even waste management, nuclear energy as an alternative source of energy should be used. The nuclear power option once again is appealing to some opinion leaders in the world. As an alternative to fossil fuels and looming energy crisis, we can find a solution to the problem of climate change, environmental degradation, and fossil fuel dependency, while guaranteeing equitable, sustainable development. Many problems stand in the way of this so called renaissance, not least the mammoth costs involved and the fact that no safe system has yet been devised for the long-term storage of nuclear wastes. Furthermore despite many improvements in the safety of nuclear power plants, worries persist about the risk of nuclear accidents such as those that occurred at Three Mile Island in USA in 1979 and Chernobyl in Ukraine in 1986. However, this alternative source of energy will pose a political problem in that nuclear power plant could be used for both military and economic purposes. It is observed that all attempts, so far, to produce enough electricity power for its citizens have hit the rocks in this country, Nigeria, due to various reasons including inefficiency and corruption. The purpose of this paper is to urge Nigeria (and other countries like it) not to give up its efforts to generate sufficient electric power by the usual traditional methods (coal, solar, wind, etc) but to continue to try until success has been achieved in the short term and to vigorously endeavour to go nuclear in the long term since nuclear generation of electricity is the ultimate in power supply. The paper also shows how the nuclear program has been achieved in some other countries and how Nigeria can follow suit in the development of nuclear energy for peaceful purposes.Item 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 Assessment of gamma-radiation attenuation characteristics of Bi2O3 – B2O3 – SiO2 – Na2O glasses using Geant4 simulation code.(SPRINGER, 2021) Sayyed, M. I.,; OLARINOYE, OYELEKE; Elsafi, M.This work aims to study the radiation shielding properties of Bi2O3–B2O3–SiO2–Na2O glasses (coded as BBS-glasses) using the Geant4 simulation and to determine the effect of the Bi2O3 content on the attenuation capability of the glasses. The mass attenuation coefficient (MAC) of BBS-glasses was estimated by the Monte Carlo simulations in Geant4, and the simulated results were validated by XCOM software. The maximum relative difference between the two approaches throughout the considered gamma-ray energies was 1.05, 1.20, 1.40, 1.52, 1.21, and 1.5%, respectively, for BBS-0–BBS-5, which means that MACestimated through the Geant4 simulation and XCOM are in good agreement; hence, the simulation results are accurate. At each investigated energy, the linear attenuation coefficient value increases with Bi2O3 as a result of the higher molecular weight of Bi2O3, hence higher electron–photon interactions. The effective atomic number varies from 7.65–9.37, 19.64–66.66, 29.01–73.92, 36.54–76.76, 42.72–78.29, and 47.89–79.23 for BBS-0–BBS-5, respectively. The half value layer for the selected glasses followed the trend: (HVL)BBS-5 <(HVL)BBS-4<(HVL)BBS-3 <(HVL)BBS-2 <(HVL)BBS-1 <(HVL)BBS-0. The transmission factor reduces as the thickness of the glasses increases, and the Bi2O3 content in the glasses greatly improved their photon shielding and protection ability. The comparison between the mean free path of the selected glasses with other materials revealed that BBS-5 is a better photon shield than BC and RS-360 commercial glass shieldsItem ASSESSMENT OF NATURAL RADIOACTIVITY LEVELS AND RADIATION HAZARDS IN THE TERTIARY INSTITUTIONS IN MINNA, NIGER STATE, NIGERIA.(2012) Kolo, M. T.,; Baba-Kutigi, A. N.,; OLARINOYE, OYELEKE; Sharifat, I.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 Crystal structure refinement of co-doped Ba0.88Ca0.12Ti0.975Sn0.025O3 ceramic(2017) Umaru Ahmadu; OLARINOYE, OYELEKE; Moses Agida; Auwal M. MuhammadBa/Ca-doped barium titanate has been prepared by solid state reaction to produce Ba0.88Ca0.12 Ti0.975Sn0.025O3(BCST) ceramics. Five samples were irradiated using neutron fluence of 8.1 106, 9.72 107, 8.75 108, 6.99 109 and 1.4 1010 n/cm2 (BCST-06 to-10). The structure and phase compositions of the control (BCST) and irradiated samples were determined by X-ray diffraction and indicate the presence of a majorly single phase tetragonal barium titanate (S.G.P4mm) with a minor phase CaTiO3 (orthorhombic). However, Rietveld refinement using GSAS II suite of programs indicates a tetragonality ratio (c/a ¼ 0.996) which is pseudocubic with a reduction in volume of 0.03% in the control compared to pristine BT. The irradiated samples exhibited changes in tetragonality (maximum of 0.82%) and variation in volume (0.58%, maximum) over the range of fluence investigated. A complete vacancy was observed in the Ca site of BCST10 but not in the oxygen sites while the occupancies of other metal sites varied. The substitution of Sn is expected to lead to a lower transition temperature and an increase in dielectric constant near the transition temperature of the control. While the changes in volume, tetragonality and occupancy of the irradiated samples are expected to affect their electromechanical properties due to changes in the Ti octahedra which would lead to a slight degradation in device performance.Item Doped Metal Oxide Thin Films for Enhanced Solar Energy Applications(Springer, 2021) Eze, C. N.; Obodoa, R. M; Ezugwu, S. C; Ezemaa, F .I.Solar energy is energy from the sun and its provision is in abundance without payments. It is renewable and more promising than its counterpart energy source called fossil fuels. Fossil fuels have energy crises ranging from inadequacy to depletion, pollution etc. This solar energy could be technically collected, utilized but there could still be an improved method of collecting the solar energy for more advanced utilization called solar energy. Achieving this by the process of doping metal oxide thin films with impurities like carbon derivatives, organic synthetic dyes etc. will harnesses dopant characteristics for optimal performance. The doped materials help in controlling the composition and structure of dopants, which enhance their performance. The metal oxide semiconductor thin films are synthesized via varieties of processes on working active layer materials with stable interfaces for solar energy conversion and versatile applications in several areas valuable for humankind.Item Effect of Nd3+ ions on radiation attenuation properties of PbF2 – TeO2 – WO3 glass system for shielding applications.(ELSEVIER, 2021) Buriahi, M. S.,; Alomairy, S., Mutuwong, C., Boukhris, I.,; OLARINOYE, OYELEKE; Tonguç, B. T.Item Elastic moduli, photon, neutron, and proton shielding parameters of tellurite bismo-vanadate (TeO2–V2O5–Bi2O3) semiconductor glasses(ELSEVIER, 2020) Y.S. Rammah; OLARINOYE, OYELEKE; F.I. El-Agawany; A. El-Adawya; A. Gamala,; El Sayed YousefIn this research, elastic moduli, photon, neutron, proton, and alpha particle shielding parameters for tellurite bismo-vanadate (TeO2–V2O5–Bi2O3) were estimated and theoretically presented. Makishima–Mackenzie's (M-M) model and Phy-X/PSD software were used to achieve the required calculations. Young's modulus varied from 72.68 to 59.41 GPa while shear modulus varied from 28.75 to 23.66 GPa. Bulk modulus changed from 51.34 to 40.51 GPa, while Poisson's ratio changed from 0.264 to 0.255. The trend of the projected range for alpha and proton particles follows the order: (TVB00)Range > (TVB05)Range > (TVB10)Range > (TVB15)Range > (TVB20)Range > (TVB25)Range. The mass attenuation coefficient of the TVB glasses follows the order: (TVB00)μm<(TVB05)μm < (TVB10) μm < (TVB15) μm < (TVB20) μm < (TVB25) μm at all energies. The MFP follows a similar trend as HVT, where TVB00 glass has the highest MFP and HVT among the considered glasses. The lowest range of Zeff was achieved TVB00 glass and the highest for TVB25 glass. The f-factor of the TVB-glasses were almost equal due to similar number of electrons per unit mass. The variations in buildup factors with photon energy were identical for all glass materials and penetration depth (mfp). Results revealed that the inclusion and increase of Bi in the TVB-glass systems improves its radiation shielding capacity.Item Environment friendly La3+ ions doped phosphate glasses/glass-ceramics for gamma radiation shielding: Their potential in nuclear safety applications(ELSEVIER, 2020) Y.S. Rammaha,; OLARINOYE, OYELEKE; F.I. El-Agawany; A. El-Adawy,; El Sayed YousefGamma-photon, neutron, and proton shielding parameters of La3+ ions doped multicomponent phosphate glasses/glass-ceramics of composition 50P2O5–30Sb2O3–10CaO–5Al2O3–5TeO2+xLa2O3 (La0–La5): x = 0–5 in steps of 1 mol% have been evaluated. These parameters were evaluated utilizing the WinXcom and EXABCal computer codes. Results revealed that the maximum values of MAC were 25.72, 26.85, 27.39, 27.91, and 28.41 cm2/g for La0–La5, respectively. Furthermore, the maximum and minimum values of LAC were obtained at 15 keV and 10 MeV, respectively with values of 91.82 and 0.107 cm−1, 94.67 and 0.108 cm−1, 98.55 and 0.111 cm−1, 101.62 and 0.113 cm−1, 105.22 and 0.115 cm−1, 107.96 and 0.116 cm−1. Values of HVL and MFP were varied according to the order (La5)HVL < (La4)HVL < (La3)HVL < (La2)HVL < (La1)HVL < (La0)HVL for all energies. The Zeff values were found to be maximum at 0.06 MeV and varied from 29.08 to 30.28 for La0 to La5, while the least values of Zeff were recorded at 1.5 MeV and varied from 14.88 to 15.53 for La0 to La5 samples. The buildup factors (B) at 15 MeV followed the trend (La0)B < (La1)B < (La2)B < (La3)B < (La4)B < (La5)B. The values of Rfor fast neutrons were 0.0911, 0.0989, 0.1078, 0.1157, 0.1242, and 0.1316 cm−1 for La0– La5, respectively. The maximum range of proton was obtained at the maximum kinetic energy (10 MeV) having the values: 0.574, 0.569, 0.559, 0.553, 0.544, and 0.540 mm for La0– La5, respectively. Therefore, the increase of La3+ doping in La0–La5 samples has a positive influence on their radiation shielding capability. It can be concluded that, La0–La5 samples can attenuate photons, neutrons, alpha particles, and protons and as such, they can be applied successfully in nuclear shielding applications.Item 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.Item 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 Factors Influencing Patient Dose in Diagnostic Radiography.(SET, 2008) OLARINOYE, OYELEKE; Igwe, KItem 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 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 He+ induced changes in the surface structure and optical properties of RF-sputtered amorphous alumina thin films(ELSEVIER, 2016) F.O. OGUNDARE; OLARINOYE, OYELEKEHigh quality 50 nmthickstoichiometric amorphous aluminium oxide films were reactively sputtered on micro scope glass slide substrates. The films were exposed to energetic (2.20 MeV) He+ at different ion fluences of 6×1012 ion/cm2;1×1013 ion/cm2;2×1013 ion/cm2;3×1013 ion/cm2; and 4 × 1013 ion/cm2. The effect of the ion irradiation on the optical, structural phase and surface properties of the alumina films was investigated via UV–VIS–NIRspectroscopy,X-raydiffraction analysis and theatomicforcemicroscopyrespectively. Thetrans missionandabsorptionspectraoftheirradiatedfilmsshowedvariationthatdependedonionfluence.Therefrac tive index, extinction coefficient, optical conductivity, dielectric constant and energy loss functions of the films were also affected by He+ irradiation. Optical band gap and films' structural phase were however not altered bytheionirradiation. The variation in optical constants induced by radiation was attributed to electronic excita tion and increase in surface roughness of the films