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      • SCIESCOPUSKCI등재

        Enhancement of nuclear radiation shielding and mechanical properties of YBiBO<sub>3</sub> glasses using La<sub>2</sub>O<sub>3</sub>

        Issa, Shams A.M.,Ali, Atif Mossad,Tekin, H.O.,Saddeek, Y.B.,Al-Hajry, Ali,Algarni, Hamed,Susoy, G. Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.6

        In this study, nuclear radiation shielding and rigidity parameters of Y (0.1-x)B0.6Bi1.8O3La2x glassy system were investigated in order to determine it's suitability for use as nuclear radiation shielding materials. Therefore, a group of bismuth borate glass samples with La<sub>2</sub>O<sub>3</sub> additive were synthesized using the technique of melt quenching. According to the results, the increase of the La<sub>2</sub>O<sub>3</sub> additive increases the density of the glass samples and the mass attenuation coefficient (μ<sub>m</sub>) values, whereas the half-value layer (HVL) and mean free path (MFP) values decrease. The effective atomic number (Z<sub>eff</sub>) is also enhanced with an increment of both mass removal cross section for neutron (Σ<sub>R</sub>) and absorption neutron scattering cross section (σ<sub>abs</sub>). In addition to the other parameters, rigidity parameter values were theoretically examined. The increase of La<sub>2</sub>O<sub>3</sub> causes some other important magnitudes to increase. These are the average crosslink density, the number of bonds per unit volume, as well as the stretching force constant values of these glass samples. These results are in concordance with the increase of elastic moduli in terms of the Makishima-Mackenzie model. This model showed an increase in the rigidity of the glass samples as a function of La<sub>2</sub>O<sub>3</sub>.

      • KCI등재

        Investigations of radiation shielding using Monte Carlo method and elastic properties of PbO-SiO2-B2O3-Na2O glasses

        Shams A.M. Issa,Yasser B. Saddeek,H.O. Tekin,M.I. Sayyed,Khamies saber Shaaban 한국물리학회 2018 Current Applied Physics Vol.18 No.6

        Several physical parameters such as the packing density (PD), oxygen molar volume (OMV), oxygen packing density (OPD) and the elastic moduli of the quaternary glass system xPbO-(30-x)SiO2-46.67B2O3-23.33Na2O (x = 0, 5, 10 and 15 mol%) have been evaluated. The elastic moduli were computed according to Makishima-Mackenzie model and Rocherulle model. The values of these moduli have been compared to their experimental values. Moreover, different shielding parameters such as mass attenuation coefficients (MAC), half value layer (HVL), mean free path (MFP), effective atomic numbers (EAN), effective electron densities (EED) and buildup factors have been evaluated using the WinXcom program in the energy range 0.015–15 MeV for the quaternary studied glass system. The MAC values have been compared with MCNPX (version 2.6.0) Monte Carlo code. Besides, mass stopping power (MSP) for proton, alpha and electron as well as the removal cross section for fast neutron (∑R) have been calculated. The results observed that the composition has the highest value of PbO (15 mol %) showed excellent nuclear radiation shielding and elastic properties.

      • Distribution of Natural Radionuclide and Radiation Hazards of Building Materials Used in Assiut, Egypt

        Shams Issa,A. M. A. Mostafa 보안공학연구지원센터 2015 International Journal of Bio-Science and Bio-Techn Vol.7 No.6

        The concentration of the naturally occurring radionuclides 226Ra, 232Th and 40K have been measured in Clay (C), gypsum (G), limestone (L), sand (S), brick (B), soil (So), cement (Ce), which are used as building materials in Assiut, Egypt, using gamma spectrometry employing a 3×3 inch scintillation NaI (Tl) detector. The radium equivalent activity (Raeq), indoor gamma absorbed dose rate (D), annual effective dose (An), (AUI), alpha index (Iα), gamma index (Iγ), external radiation hazard index (Hex), internal radiation hazard index (Hin), representative level index (RLI), excess lifetime cancer risk (ELCR) and annual gonadal dose equivalent (AGDE) associated with the natural radionuclides are calculated to assess the radiation hazard of the natural radioactivity in the building materials. Basic statistics (skewness and Kurtosis) and frequency distributions for all radionuclides were used to describe the statistical characteristics of the radionuclide activities.

      • KCI등재

        A rapid and direct method for half value layer calculations for nuclear safety studies using MCNPX Monte Carlo code

        Tekin H.O.,ALMisned Ghada,Issa Shams A.M.,Zakaly Hesham M.H. 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.9

        Half Value Layer calculations theoretically need prior specification of linear attenuation calculations, since the HVL value is derived by dividing ln(2) by the linear attenuation coefficient. The purpose of this study was to establish a direct computational model for determining HVL, a vital parameter in nuclear radiation safety studies and shielding material design. Accordingly, a typical gamma-ray transmission setup has been modeled using MCNPX (version 2.4.0) general-purpose Monte Carlo code. The MCNPX code's INPUT file was designed with two detection locations for primary and secondary gamma-rays, as well as attenuator material between those detectors. Next, Half Value Layer values of some well-known gamma-ray shielding materials such as lead and ordinary concrete have been calculated throughout a broad gamma-ray energy range. The outcomes were then compared to data from the National Institute of Standards and Technology. The Half Value Layer values obtained from MCNPX were reported to be highly compatible with the HVL values obtained from the NIST standard database. Our results indicate that the developed INPUT file may be utilized for direct computations of Half Value Layer values for nuclear safety assessments as well as medical radiation applications. In conclusion, advanced simulation methods such as the Monte Carlo code are very powerful and useful instruments that should be considered for daily radiation safety measures. The modeled MCNPX input file will be provided to the scientific community upon reasonable request.

      • SCIESCOPUSKCI등재

        Physical and nuclear shielding properties of newly synthesized magnesium oxide and zinc oxide nanoparticles

        Rashad, M.,Tekin, H.O.,Zakaly, Hesham MH.,Pyshkina, Mariia,Issa, Shams A.M.,Susoy, G. Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.9

        Magnesium oxide (MgO) and Zinc oxide (ZnO) nanoparticles (NPs) have been successfully synthesized by solid-solid reaction method. The structural properties of ZnO and MgO NPs were studied using X-ray diffraction (XRD) and scanning electron microscopy (SEM). XRD results indicated a formation of pure MgO and ZnO NPs. The mean diameter values of the agglomerated particles were around to be 70 and 50 nm for MgO and ZnO NPs, respectively using SEM analysis. Further, a wide-range of nuclear radiation shielding investigation for gamma-ray and fast neutrons have been studied for Magnesium oxide (MgO) and Zinc oxide (ZnO) samples. FLUKA and Microshield codes have been employed for the determination of mass attenuation coefficients (μ<sub>m</sub>) and transmission factors (TF) of Magnesium oxide (MgO) and Zinc oxide (ZnO) samples. The calculated values for mass attenuation coefficients (μ<sub>m</sub>) were utilized to determine other vital shielding properties against gamma-ray radiation. Moreover, the results showed that Zinc oxide (ZnO) nanoparticles with the lowest diameter value as 50 nm had a satisfactory capacity in nuclear radiation shielding.

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