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Item Survey of Gross Alpha and Gross Beta Radioactivity in Sachet water Hawked in Minna, Niger State.(2009) Kolo, M. T.,; Baba-kutugi; OLARINOYE, OYELEKE; Sharifat, I.Item Recycling potential of cathode ray tubes (CRTs) waste glasses based on Bi2O3 addition strategies(ELSEVIER, 2022) Al-Buriahi, M. S., Kavas, T., Kavaz, E., Kurtulus, R.,; OLARINOYE, OYELEKECathode-ray tubes (CRTs) from computer monitors and television sets are considered as one of the main sources of waste materials worldwide. Therefore, a new application for such out of use materials is required to solve the relatively huge amount of this waste. In this paper, the popular melt-quench technique was used to synthesis glass samples with the structure: xBi2O3–(100-x) waste CRTs (where x =0, 10 & 20 wt%) and designated as CRT- Bi0, CRT-Bi10, and CRT-Bi20 accordingly. The physical, structural, optical and radiation absorption competence of the glasses were investigated. The XRD analysis of the glasses reveals an amorphous structure while the mass density increased linearly with the Bi2O3 content of the glasses from 2.86 to 3.08 g/cm3. The optical absorbance of the glasses initially increased and later declined in the visible region as the weight fraction of Bi2O3 increased. The direct optical bandgap Eg values were found to be 3.26, 2.72, and 2.64 eV whereas the indirect Eg values were equal to 3.15, 2.30, and 2.26 eV for CRT-Bi0, CRT-Bi10, and CRT-Bi20, respectively. The gamma-ray interaction parameters of the glasses obtained through FLUKA simulations and XCOM computation showed that mass attenuation falls within the range 0.6991–0.0256, 1.1426–0.0276, 1.5860–0.0301 cm2/g for photon energy range 0.1–10 MeV. Generally, the computed gamma ray interaction quantities show that the gamma ray shielding ability of the CRT-Bi glasses follows the order: CRT-Bi0Item Evaluation of radioactivity concentration of some selected mineral rocks from Mayo-Belwa Local Government Area of Adamawa State, Nigeria.(DUJOPAS, 2022) Oduh, I. O., Joseph, S. R.,; OLARINOYE, OYELEKE; Kolo, M. T.,Radiation from natural sources is constantly present around people and their surroundings. Natural Occurring Radioactive Materials (NORM) present in rock, soil and underground water are the major sources of this radiation. In this study, radioactivity concentration of 238U, 232Th, and 40K from Ten (10) different Granite (GN), Gneiss (GS), and Migmatite (MG) rocks samples obtained from Mayo Belwa Local Government Area of Adamawa State were evaluated using a well calibrated and shielded Canberra 3 x 3 inch NaI(Tl) detector at the National Institute of Radiation Protection and Research (NIRPR), University of Ibadan. Rock samples were cleaned, pulverised and placed in the detector for counting, and based on standard expressions, the radionuclide content of the granite rock samples were evaluated. The result shows that the activity concentration of 238U, 232Th, and 40K in GN samples varies from 62.44 – 117.67 Bq/kg, 76.59 – 165.58 Bq/kg, and 688.03 – 1472.42 Bq/kg with corresponding mean of 74.59 ± 3.12, 104.41 ± 3.12, and 950.16 ± 3.12 Bq/kg. Activity concentration of 238U, 232Th, and 40K in GS samples ranges from 19.23 – 36.49 Bq/kg, 29.06 – 49.42 Bq/kg, and 310 – 924.21 Bq/kg with corresponding mean of 28.1 ± 5.36Bq/kg, 38.92 ± 6.38 Bq/kg, and 664.21 ±178.14 Bq/kg. Activity concentration of 238U, 232Th, and 40K in MG samples ranges from 32.11 – 74.73 Bq/kg, 40.79 – 105.87 Bq/kg, and 453.34 – 1040.77 Bq/kg with corresponding mean of 50.19 ± 14.35 Bq/kg, 60.50 ± 19.96 Bq/kg, and 714.88 ± 200.37 Bq/kg. The mean activity from this study are higher than the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) global mean of 238U (32 Bq/kg), 232Th (45 Bq/kg), and 40K (420 Bq/kg) in soil and rock samples except for 238U and 232Th in GS samples which are lower than the recommended standards. The results signifies that usage of such rocks as building construction raw materials might pose radiological hazards in the long run. Therefore, mineral content of the rock responsible for the high radionuclide concentration should be investigated.Item Photon and Fast Neutron Transmission Parameters of Metakaolin Doped Concrete.(BPC, 2021) OLARINOYE, OYELEKE; Idris, M. M., & KureRadiation-shielding properties of metakaolin doped concrete samples were investigated in this report. The gamma photon mass attenuation coefficients and exposure buildup factor of the samples were determined theoretically using WinXcom and EXABCal software respectively for the energy range of 15 keV - 15 MeV and fast neutron removal cross section for the concrete sample was evaluated. Results indicated that, oxides of silicon, aluminum, calcium and iron determined through the energy dispersive X-ray fluorescence spectrometric analysis constitute more than 85% of the chemical composition of the concrete samples. The oxides contribute 85.46, 86.47, 87.55, 88.75, and 86.15 % of the total chemical oxides in MK00, MK05, MK10, MK15, and MK20 respectively. Densities of the prepared MK doped concrete were in the range of 2.575-2.667 g/cm3. Compressive stress of prepared MK doped concretes increased consistently with the curing period for each concrete sample. CS grew from 8.71 - 10.63, 8.84 - 10.83, 9.44 - 11.22, 10.89 - 11.53, and 10.76 - 11.43 MPa for MK00, MK05, MK10, MK15, and MK20 respectively as the period extends from 7 to 28 days. Mass attenuation coefficient decrease steadily with an increase in energy up to about 0.1 MeV and the decrease become smaller beyond this energy with increasing energy for all the mixtures. Fast neutron removal cross section results indicate that MK10 (0.07693 cm-1) has the highest value of ΣR followed by MK15 (0.07628 cm-1) and MK20 (0.07537 cm-1) while MK00 (0.07380 cm-1) and MK05 (0.07404 cm-1) have approximately the same value. It was found that MK10 concrete has the best gamma radiation and fast neutron shielding ability among the MK doped concrete under study.Item Klein–Nishina formula and Monte Carlo method for evaluating the gamma attenuation properties of Zn, Ba, Te and Bi elements.(ELSEVIER, 2021) Al-Buriahi, M. S., Alrowaili, Z. A., Ezzine, S.,; OLARINOYE, OYELEKE; Alomairy, S., Mutuwong, C., & Tonguç, B. T.In this work, the Klein–Nishina (K–N) approach was used to evaluate the electronic, atomic, and energy-transfer cross sections of four elements, namely, zinc (Zn), tellurium (Te), barium (Ba), and bismuth (Bi), for different photon energies (0.662 MeV, 0.835 MeV, 1.170 MeV, 1.330 MeV, and 1.600 MeV). The obtained results were compared with the Monte Carlo method (Geant4 simulation) in terms of mass attenuation and mass energy-transfer coefficients. The results show that the K–N approach and Geant4 simulations are in good agreement for the entire energy range considered. As the photon energy increased from 0.662 MeVto 1.600 MeV, the values of the energy-transfer cross sections decreased from 81.135 cm2 to 69.184 cm2 in the case of Bi, from 50.832 cm2 to 43.344 cm2 for Te, from 54.742 cm2 to 46.678 cm2 for Ba, and from 29.326 cm2 to 25.006 cm2 for Zn. The obtained results and the detailed information of the attenuation properties for the studied elements would be helpful in developing a new generation of shielding materials against gamma rays.Item Synthesis, optical, and radiation attenuation properties of CaF2-TeO2-Na2B4O7-CuO glass system for advanced shielding applications.(SPRINGER, 2021) Sekhar, K.C., Narsimlu, N., Al-Buriahi, M.S. H.H. Yakout,; OLARINOYE, OYELEKE; Sultan Alomairy, & M.D. Shareefudinfabricated a new series of sodium tetraborate (Na2B4O7) containing TeO2, CaF2, and CuO for advanced performance in optical and radiation applications. PHILIPS (Xpert PRO)X-ray diffractometer was employed at room temperature (RT) to investigate the fabricated specimens’ amorphous nature. Furthermore, UV–visible spectra and EPR spectra (~9.7 GHz and field modulation 100 kHz) were also achieved for the involved glass system. Moreover, FLUKA Monte Carlo simulations were successfully designed to describe the gamma transmission properties through the fabricated glass specimens. The results reveal that the optical band gap (Eg) decreased from 3.079 to 2.605 eV as the CaF2 content increased from 0 to 50 mol %. In the EPR spectra, fourth parallel hyperfine splittings in the high field are merged with the perpendicular hyperfine splitting’s resulting in a single intense line. The gamma transmission studies show that the gamma absorption in the present glasses were highest at the least energy with the value of within the range: 0.0789–0.0229, 0.0789–0.0232, 0.0790–0.0236, 0.0790–0.0241, 0.0791–0.0246, and 0.0792–0.0253 cm2g−1 for CaF2 content of 0, 10, 20, 30, 40, and 50 mol %, respectively. It can be concluded that the present fabricated glass system has excellent and promising properties to use for optical and radiation applicationsItem Photon, proton, and neutron shielding capacity of optical tellurite-vanadate glass systems: Theoretical investigation.(ELSEVIER, 2021) Rammah, Y. S.,; OLARINOYE, OYELEKE; El-Agawany, F. I., & El-Adawy, A.The influence of density and molar concentration of Ag2O on photon, proton, neutron, and alpha particle shielding capacity of tellurite-vanadate-silver glass systems with the form 40TeO2+(60-x)V2O5+xAg2O: x = 0–50 mol% (encoded as TVAg0- TVAg50) was evaluated and analyzed in a wide range of energy (0.015–15 MeV). Linear and mass attenuation coefficients (μ, μm), half value thickness (HVT), mean free path (MFP), and effective atomic number (Zeff) were evaluated via the free online program–Phy-X/PSD, while EBF and EABF were computed via EXABCal software. The maximum μm was obtained at the least photon energy (15 keV) with values equal to 29.702, 31.371, 32.949, 34.443, 35.86, and 37.205 cm2g-1 for TVAg0, TVAg10, TVAg20, TVAg30, TVAg40, and TVAg50, respectively. Generally, The μm of the glass’s trends in the order: (μm)TVAg0 <(μm)TVAg10 <(μm)TVAg20 <(μm)TVAg30 <(μm)TVAg40 <(μm)TVAg50. The trend of μ amongst the glasses is like that of the mass attenuation coefficient. The values of the maximum MFP varied from 9.757 to 4.53 cm for TVAg0 and TVAg50, respectively. The HVT trend of TVAg-glasses obeys the order: (HVT)TVAg0 >(HVT)TVAg10 >(HVT)TVAg20 > (HVT)TVAg30 >(HVT)TVAg40 >(HVT)TVAg50. The range of Zeff for the glasses varied from: 14.8 to 42.38 for TVAg0 glass and from 26.06 to 47.63 for TVAg50 glass. The f-factor of the TVAg-glasses were lower than unity except that of TVAg50 at 5 MeV. The variations in buildup factors with photon energy is alike for all glass materials and depth of penetration (mfp). The projected range (PR) followed the order: (PR)TVAg0 >(PR)TVAg10 >(PR)TVAg20 > (PR)TVAg30 >(PR)TVAg40 >(PR)TVAg50 for both proton and α-particle. Mass stopping power (MSP) is inversely proportional to the atomic number of the target (TAVg-glasses). Results confirmed that density and molar concentration of Ag2O plays an important role for improving the radiation shielding capacity of the investigated TAVg-glasses.Item Effects of TeO2 and B2O3 on photon, neutron, and charged particle transmission properties of Bi2O3-BaO-LiF glass system.(SPRINGER, 2021) OLARINOYE, OYELEKE; Alomairy, S., Sriwunkum, C., Hegazy, H. H., & Al-Buriahi, M. S.This work investigates the effects of TeO2 and B2O3 on photon, neutron, and charged particle transmission properties of Bi2O3BaO-LiF glass system. Photon transmission parameters were obtained via narrow beam setup simulation via FLUKA and those obtained from experimentally proved XCOM calculations. The attenuation factors of μ=ρ IS and μ=ρ PP control the value of μ=ρ at energies greater than 1.5 MeV; however, the region of influence differs for both absorption processes. While μ=ρ IS peaks occur at 3 MeV, the influence of μ=ρ PP becomes appreciable at E > 5 MeV. The values of linear attenuation factor (μ) ranged from 0.2119–0.5283, 0.2085–0.5248, 0.1837–0.4676, 0.1639–0.4223, 0.1519–0.3971, 0.1370–0.3638, and 0.1222–0.3315 cm-1 as B2O3 increased from 0 to 60 mol % with step of 10, respectively. The spectra of projected range (R) of the ions and CSDA range of electrons show that the TSP of electrons in the glasses increases as B2O3 increased from 0 to 60 mol % for energy lower than 5 MeV; however, it reverses at 10 MeV. The ability of the present glass system for stopping the transmission of various radiation beams reveals its potential use for shielding applications in medical and nuclear facilities.Item Role of heavy metal oxides on the radiation attenuation properties of newly developed TBBE-X glasses by computational methods.(2021) Al-Buriahi, M. S., Alzahrani, J. S.,; OLARINOYE, OYELEKE; Akyildirim, H., Alomairy, S., Kebaili, I., ... & Mutuwong, C.Geant4simulationsandseveraltheoreticalapproachessuchasWinXCOMandESTARwereusedin this worktounderstandtheroleofheavymetaloxidesontheradiationattenuationfeaturesofnewly developedTBBE-Xglasseswhichareintheformof19.5TeO2-30B2O3-30BaO-0.5Er2O3-20X.HereXstandsforSrO,Al2O3,CdO,ZnO,PbOandBi2O3.AccordingtoX(modifieroxide),theglasssamples werelabelledasTBBE-S,TBBE-A,TBBE-C,TBBE-Z,TBBE-P,andTBBE-B.Variousattenuation features suchasmassattenuationcoefficient(MAC),buildupfactors,equivalentandeffectiveatomic numbers,halfvaluelayer(HVL),andneutroncrosssectionwereinvestigated.Theinclusionofhigh atomicnumberanddenseatomsinthemodifiers(PbOandBi2O3)inTBBE-PandTBBE-Bexplains whytheenergyfortheonsetofincrementinMACwasearliestamongtheinvestigatedglasses.Ata photonenergyof15keV,HVLof TBBE-S,TBBE-A,TBBE-Z,TBBE-C,TBBE-P,andTBBE-Bwere 4.67, 5.02, 4.40,3.91,3.53, and3.31cmrespectively.ItisfoundthattheTBBE-Xglasseshave promisingshieldingpropertiesagainstgammaradiationcomparingtodifferentspeciesofcommercial glasses andconcrete.TheoutcomesalsorevealthattheTBBE-Xspecimensarecomparativelybetter shields against fastneutroncomparedtoclassicalshieldslikegraphite,water,andordinaryconcrete. Therefore,theTBBE-Xglasseshavepromisingshieldingpropertiesandcanbeappliedinshielding applications againstgammaraysandneutronsbeamItem Effect of Ag2O/V2O5substitution ontheradiation shielding ability of tellurite glass system via XCOM approachand and FLUKAsimulationS(SPRINGER, 2021) OLARINOYE, OYELEKE; Alomairy, S., Sriwunkum, C., & Al-Buriahi, M. S.ThisstudyfocusesontheeffectofAg2O/V2O5substitutionontheradiationshieldingabilityoftellurite glass systemwiththechemicalcompositionofxAg2O+40TeO2+(60−x)V2O5with0<x< 50mol%.FLUKAcodewassuccessfullyemployedforsimulationtheradiationinteractionparameters of theglass systems.Theresultsofthesimulationswerecomparablewiththepredicationsoftheory. Thereafter, several empirical equationswereusedtostudytheshieldingabilityoftheglasssystemsagainst neutronsandchargedparticles.Theresultsindicatethatlinearattenuationcoefficientchangeswithenergy andreachesmaximumat0.6MeV(minimumat10MeV)withthevaluesof0.2806(0.109),0.3181(0.121), 0.3771(0.1498),0.409(0.168),0.4588(0.1911),and0.5162(0.2180)forx=0,10,20,30,40,and50mol%, respectively. Beyond5MeV,thegammarayconstantwasfoundintheorderof G = x 50 ( ) > G = x 40 ( ) > G = x 30 ( ) > G = x 20 ( ) > G = x 10 ( ) > G = . x 0 ( ) Forallthechargedparticles,theprojectilerangewasnotedin the orderof(R)x=0>(R)x=10>(R)x=20>(R)x=30>(R)x=40>(R)x=50.Finally,weprovidean extensive comparativestudybetweenAVT-glasssystemsandstandardtraditionalmaterials.Theobtained resultssuggestthesampleofx=50mol%asthebestphoton,fastneutronandchargedparticleshield amongstthepresentglasssystems.Hence,AVT6couldbeusedinradiationsafetyapplicationsasashield
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