Enhancement of nuclear radiation shielding and mechanical properties of YBiBO3 glasses using La2O3

Issa Shams A.M.; Ali Atif Mossad; Tekin H.O.; Saddeek Y.B.; Al-Hajry Ali; Algarni Hamed; Susoy G.

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자료유형: 학술저널

저자정보: Issa Shams A.M. Ali Atif Mossad Tekin H.O. Saddeek Y.B. Al-Hajry Ali Algarni Hamed Susoy G.

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제6호

발행연도: 2020.1

수록면: 1,297 - 1,303 (7page)

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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 La2O3 additive were synthesized using the technique of melt quenching. According to the results, the increase of the La2O3 additive increases the density of the glass samples and the mass attenuation coefﬁcient (mm) values, whereas the half-value layer (HVL) and mean free path (MFP) values decrease. The effective atomic number (Zeff) is also enhanced with an increment of both mass removal cross section for neutron (PR) and absorption neutron scattering cross section (sabs). In addition to the other parameters, rigidity parameter values were theoreticallyexamined. The increase of La2O3 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 La2O3

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참고문헌 신청

H.O. Tekin / 2016 / MCNP-X Monte Carlo code application for mass attenuation coefficients of concrete at different energies by modeling 3 3 inch NaI(Tl)detector and comparison with XCOM and Monte Carlo data / Sci. Technol. Nucl. Install. :7

H. O. Tekin / 2017 / Effects of micro-sized and nano-sized WO3on mass attenuation coefficients of concrete by using MCNPX code / Appl. Radiat. Isot 121:122~125

H. O. Tekin / 2017 / Simulations of mass attenuation coefficients for shielding materials using the MCNP-X code. Nuclear Science and Techniques / Nucl. Sci. Tech 28:95

H. O. Tekin / 2018 / Gamma radiation shielding properties of the hematite-serpentine concrete blended with WO3 and Bi2O3 micro and nano particles using MCNPX code / Radiat. Phys. Chem 150:95~100

F. Akman / 2019 / Investigation of photon shielding performances of some selected alloys by experimental data, theoretical and MCNPX code in the energy range of 81 keV-1333 keV / J. Alloy. Comp 772:516~524

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