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Author: search.filters.author.OLARINOYE, OYELEKEEnd date: 22

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    An insight into advanced glass systems for radiation shielding applications: A review on different modifiers and heavy metal oxides-based glasses.
    (CELL PRESS, 2024) Al-Buriahi, M. S., Kurtulus, R., Eke, C., Alomairy, S.; OLARINOYE, OYELEKE
    Ionizing radiation from natural and many synthetic sources is a remarkable tool in many scientific, production, quality control, food preservation, medical, security, and other technological processes. The need to protect humans (public and personnel), gadgets, the environment, and animals from the harmful effects of radiation, while maintaining and expanding the scope of application has made radiation protection an important topic to discuss. Among the methods and materials available for radiation control, shielding and the use of glass shields are the most effective and attractive methods and materials, respectively. In this report, the basic parameters for measuring shielding competences, basic shielding materials and their shortcomings, and glass shields are discussed. Five categories of glasses, namely, borate, germanate, silicate, phosphate, and tellurites, with important shielding attributes, are reviewed. The role of chemical composition, density, and mean atomic number as gamma shielding delineating factors was emphasized. The weaknesses and comparable advantages of each glass system were presented as well. The review concludes by looking at the trend and future of glass shields and research in radiation technology. The data and analysis presented in this review provides scientists and radiation protection technologist on the impact of certain chemical oxides on shielding efficacies of different glass systems.
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    Mechanical properties and radiological implications of replacing sand with waste ceramic aggregate in ordinary concrete.
    (ELSEVIER, 2024) OLARINOYE, OYELEKE; Kolo, M. T.,; Amuda, D. B., Oche, C. O., Mohammed, B., Alzahrani, J. S., & Al-Buriahi, M. S.
    The mining of aggregates for the production of concrete creates ecological problems. In this study, the effect of partially replacing sand as fine aggregate (FA) with waste ceramic tiles (WCT) on the density, compressive strength (CS), specific radioactivity of naturally occurring radioactive materials (238U, 232Th, and 40K), and the radiation shielding competence of concrete was investigated. Ordinary concrete samples consisting of cement, fine aggregate (river sand), coarse aggregate (granite), and water were prepared in 50 mm ×50 mm x 50 mm cubical steel moulds. The samples were coded as C-WCT0, C-WCT5, C-WCT10, C-WCT15, C-WCT20, and C- WCT25, representing concrete samples in which the FA component was replaced by 0, 5, 10, 15, 20, and 25% pulverized WCT, respectively. The CS and density of the samples were determined after 7-, 14-, and 28-day curing periods. The gamma spectrometric method was used to determine the specific activity of 238U, 232Th, and 40K using a hyper pure germanium detector. The photon and neutron shielding parameters of the concrete blocks were calculated with the aid of the EPICS2017 cross-section library and relevant standard formulae. The mean CS for each concrete category increase with curing age. The density of the concrete varied from 2213 kg/ m3 to 2488 kg/m3 as the FA replacement level rose to 15%. Using WCT as a partial replacement for FA altered the chemical composition and decreased the specific activities of 238U, 232Th, and 40K, in the concrete samples. C- WCT15 had the best gamma photon and fast neutron absorption features among the concrete samples. The use of WCT as aggregate in concrete production is a sustainable and environmental-friendly way of producing concrete for general civil engineering and shielding applications in medical and other radiation facilities. This study also affirms that using alternative materials with lower specific activity to replace sand is radiologically desirable in reducing the indoor radiation dose of occupants of concrete-based structures. The replacement of 15% sand by WCT produced stronger, radiologically safer, and more effective radiation absorbing concrete.
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    Assessment of Environmental Background Gamma Radiation Variation in Minna Area of Nigeria
    (Taylor and Francis, 2024) Adeiza Stephen, A.,; OLARINOYE, OYELEKE; Kolo, M. T.,; Kasim, I.
    Radiation has been acknowledged to be responsible for deleterious conditions in living tissues. Hence, environmental background gamma radiation (BGR) measurement is crucial from an environmental and health perspective. In this study, due to the absence of comprehensive background gamma radiation data and the increasing numbers of anthropogenic activities that could increase the BGR level, such as where mining activities are active. The BGR in the Minna area of Niger State, Nigeria, was measured and analyzed in this study. In-situ measurement of the background gamma radiation level was carried out using a well-calibrated portable handheld GQ GMC-500 Plus nuclear radiation detector at an elevation of about 1.0m above ground level. global positioning system from Garmin (GPSmap 78s) was adopted for identifying geographical locations. A total of 1172 points were surveyed across the study area for background environmental radiation. The BGR values ranged from 0.102 to 0.147 lSv/h, with an overall mean value of 0.126 lSv/h. The average measured dose rate was more than twice the reported world average value of 0.059 lSv/h. The annual effective dose equivalent (AEDE) for the research area was calculated to be 0.221 mSv/y on average. The mean AEDE is lower than the ICRP recommended limit. This shows that the population of the Minna area is radiologically safe based on the estimated AEDE value. Similarly, the excess lifetime cancer risk (ELCR) value ranged from 0.626�10 0.774±0.09�10 −3 −3 to 0.901�10 −3 mSv/y with a mean value of mSv/y. The mean value of AEDE is below the 0.24 mSv/y permissible limits as recommended by the International Commission on Radiological Protection (ICRP). The mean ELCR value exceeds the average world value of 0.29�10 −3 . Also, the mean organ dose values estimated for the whole body, liver, kidney, testes, bone marrow, ovaries, and lungs are 0.150±0.02, 0.102±0.01, 0.137±0.02, 0.181±0.02, 0.152±0.02, 0.128±0.02 and 0.141±0.02 mSv/y respectively. The differences in the calculated mean of BGR were attributed to natural and human factors. Geological variation is a fundamental factor that influences the changes in BGR. Human activities, mining, building materials, and the use of phosphate fertilizers in agricultural practices are responsible for the differences in BGR. The ELCR implies that terrestrial gamma radiation does not pose any immediate radiological health effects on residents of the area, but there is a tendency for long-term health hazards in the future, such as cancer, due to the dose accumulated
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    Estimation of indoor gamma radiation dose rate from concrete blocks constructed from tin mine tailings.
    (ELSEVIER, 2023) OLARINOYE, OYELEKE; Kolo, M. T.,; Shittu, H. O., & Anumah, A. S.
    The use of building materials made from geological sources contributes greatly to the indoor radiation exposure of human. As a result, it is critical for public health that building materials be screened for elevated radionuclide concentrations. This research measures the primordial radionuclide content of concrete blocks derived from mine tailings and also estimates the indoor annual effective dose rate (AEDR) and associated parameters. Furthermore, it presents a simple empirical relationship for evaluating dose rate per unit specific activity due to radionuclides from a wall of arbitrary dimensions. Twelve concrete blocks constructed using tin mine tailings as fine aggregates were collected locally and analyzed for 235U, spectrometry analysis. The concentration of 238 232Th and 40K content using gamma U ranged from 86.29 to 197.73 Bq/kg with a mean of 120.93 Bq/kg. Also, the specific activity of 232Th and 40 K is within the limits: 99.01–353.67 Bq/ kg and 500.71–1021.77 Bq/kg with mean values of 248.31 Bq/kg and 635.10 Bq/kg, respectively. Obtained dose rate per unit specific activity agreed well with data from literature. Using the derived values of dose rate per unit specific activity, the annual effective dose rate (AEDR) obtained from a typical Nigerian room varies significantly from that obtained from equations in referenced documents where a different room configuration was used. The mean AEDR from the realistic Nigerian room (3.6 × 3.6 × 3 m3 ) was higher than the world average value but less than the recommended safety limit of 1 mSvy 1 . Some of the blocks with AEDR more than the safety limits were recommended for use in superficial quantities for building construction. The model derived in this study can be applied to calculate dose rates within any room configuration.
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    Determination of structural features of different Perovskite ceramics and investigation of ionizing radiation shielding properties.
    (ELSEVIER, 2021) Slimani, Y., Hamad, M. K.,; OLARINOYE, OYELEKE; Alajerami, Y. S., Sayyed, M. I., Almessiere, M. A., & Mhareb, M. H. A.
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    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.
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    Synthesis, optical, structural, and radiation transmission properties of PbO/Bi2O3/B2O3/Fe2O3 glasses: An experimental and in silico study.
    (ELSEVIER, 2021) Sekhar, K. C., Hameed, A., Narsimlu, N., Alzahrani, J. S., Alothman, M. A.,; OLARINOYE, OYELEKE; Shareefuddin, M.
    In this paper, a new glass combination containing PbO, Bi2O3, B2O3, and Fe2O3 has been synthesized, characterized, and studied in details for advanced optical and radiation shielding applications. The PbO excess was in the step of 10% at the expense of (Bi2O3+B2O3). The physical and optical parameters were experimentally measured for each prepared glass sample. The structure characterization of the glass specimens was performed by using both FTIR and XRD. Moreover, EPR spectra were studied to give a full understanding about the valence state and interaction of paramagnetic ions. Additionally, Monte Carlo method was utilized to design the simulation setup for studying the radiation propagation through the prepared samples. The obtained results indicate that the optical band gap values were found to be high with excess of PbO content. The EPR spectra have shown a high intense resonance signal at g ≈4.2 and mild intense signal located at g ≈2.1. The magnitudes of linear attenuation coefficients for the glasses at different energies shows that maximum (minimum) value of 290.39 (0.158), 322.67 (0.168), 367.13 (0.184), 431.04 (0.207), 502.32 (0.231), and 574.34 (0.0257) cm1 was obtained for PBBF-0 – PBBF-50. This investigation lays the foundation for using the prepared glass system as a new candidate in advanced optical and shielding applications.
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    Bi2O3 reinforced B2O3 + Sb2O3 + Li2O: composition, physical, linear optical characteristics, and photon attenuation capacity.
    (ELSEVIER, 2021) Abouhaswa, A. S.,; OLARINOYE, OYELEKE; Kudrevatykh, N. V., Ahmed, E. M., & Rammah, Y. S.
    Role of Bi2O3 on the structure, physical, linear optical characteristics, and radiation protection capacity of antimony borate–lithium with the form (65- x)B2O3 ? 10Sb2O3 ? 25Li2O ? xBi2O3 x = 0 (BSLB0), 4 (BSLB4), 8 (BSLB8), 12 (BSLB12), 16 (BSLB16), 20 (BSLB20) mol% glass systems was examined. The density was increased from 2.7125 to 3.9454 g cm-3 for BSLB0 and BSLB20 glass samples, respectively. The indirect optical bandgap decreases from 2.63 to 2.45 eV, while the direct optical bandgap decreases from 3.06 to 2.89 eV. Therefore, values of the refractive index (n) were varied from 2.50 to 2.56. Both optical (roptical) and electrical (relectrical) conductivities were enhanced with increasing Bi2O3 content in the investigated glasses. The observed trend of linear attenuation coefficient (LAC) values throughout the energy spectrum was followed the sequence: (LAC)BSLB20[(LAC)BSLB16[(LAC)BSLB12[(LAC)BSLB8[(LAC)BSLB4[(LAC)BSLB0 with values in the range of 0.052–14.469, 0.062–28.291, 0.070–42.738, 0.082–61.708, 0.091–79.616, and 0.104–102.154 cm-1 for BSLB0–BSLB20 glasses, respectively. At each energy within the energy spectrum, the mean free path (MFP) and half value layer (HVL) of the BSLB-glasses were decreased in the order of increasing Bi2O3 content in the glasses. The effective atomic number (Zeff) value varies from 6.53 to 15.12, 6.76–16.32, 7.02–17.37, 7.29–18.36, 7.58–19.29, and 7.89–20.16 for BSLB0BSLB20 glasses, respectively. Therefore, BSLB-glasses possess superior photon protection capacity than ordinary (OC) and barite (BC) concretes for photons.
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    SrO-reinforced potassium sodium borophosphate bioactive glasses: Compositional, physical, spectral, structural properties and photon attenuation competence
    (ELSEVIER, 2021) Rammah, Y. S.,; OLARINOYE, OYELEKE; El-Agawany, F. I., Ibrahim, S., & Ali, A. A.
    The melt quenching process is assumed in making the glass system 45P2O5-15B2O3-22Na2O-(18-x) K2O: xSrO where x =0-12 mol%, namely as S1-S5. Compositional, physical, spectral, structural properties and radiations attenuation competences of S1-S5 bioglasses have been investigated compared to ordinary concrete (OC) cortical bone (CB) and soft tissue (ST). The density of the prepared bioactive glasses has been found to increase with an increase in the SrO content, whereas an opposite trend has been observed in the molar volume. FTIR study shows the existence of different structural groups such as BO3, BO4 and BPO4 units in the network. Optical absorption spectra of the glasses revealed that the cutoff wavelength decreases with increased in SrO content. The maximum (minimum) MAC values were 7.986 (0.021), 7.925 (0.0214), 7.863 (0.0217), 7.865 (0.0217) and 8.837 (0.022) cm2/g for S1, S2, S3, S4, and S5, respectively. The maximum value of LAC was also obtained at 15 keV with values equal to: 18.528, 18.942, 19.343, 19.898, and 20.144 cm1 respectively for S1-S5. At 0.1, 1.0, and 10 MeV, values of HVT of the glasses were 1.72, 1.54, 1.38, 1.34, and 1.14 cm for S1-S5, respectively, however, the HVT of S1–S5 were less than that of ordinary concrete (OC). The MFP was reduced as SrO content of the S1-S5 glasses increased. Results of the calculated radiation interaction parameters showed that S5 is a better photon, proton and electron absorber compared to the other four bioactive glasses in this study. Improving in photon absorption of the glasses was recorded for higher SrO content. The effect of SrO addition on photon (energy) absorption is more significant for photon energies less than 0.2 MeV. The studied bioactive glasses can function better than ordinary concrete for photon shielding applications.
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    Effect of CdO addition on photon, electron, and neutron attenuation properties of boro-tellurite glasses.
    (ELSEVIER, 2021) Al-Buriahi, M. S., Hegazy, H. H., Alresheedi, F.,; OLARINOYE, OYELEKE; Algarni, H., Tekin, H. O., & Saudi, H. A.
    This research article aims to study the effect of CdO addition on the radiation shielding characteristics of boro-tel lurite glasses in the composition of 50B2O3- (50-x) TeO2- xCdO, where x = 0, 10, 20, 30, 40 and 50 mol%. These glasses were exposed to gamma radiation and the transmitted gamma photons were evaluated for energies varying from 15 keV to 15 MeV using Geant4 simulation toolkit. The number of transmitted photons was then used to characterize the gamma shielding for the studied glasses in terms of linear/mass attenuation coefficients, MFP, Zeff, and HVL. The simulation outcomes were theoretically confirmed by using Phy-X software. The beta (electron) shielding characterization of the involved glasses was also investigated by determining the projectile range and stopping power using ESTAR software. Additionally, the fast neutron shielding characterization of the glasses was achieved by evaluating removal cross-section (ΣR). The results reveal that the CdO has a small influence on the shielding performance of the boro-tellurite glasses against gamma, beta, and neutron radiations. The shielding performance of the boro-tellurite glasses was compared with that of common shielding materials in terms of MFP. It can be concluded that the boro-tellurite glasses regardless of the concentration of CdO content have promising shielding performance to be used for radiation applications