新型(B_2O_3-Na_2O-K_2O-xBi_2O_3)玻璃的核辐射屏蔽行为和结构特性评估

Dua'a Anis Taya, Adel A. M. Saeed, Emran Eisa Saleh
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摘要

本研究采用熔淬技术制备了由 (80-x) B2O3-10Na2O-10K2O-xBi2O3(x=0、15、30、45 mol%)组成的四种玻璃样品,研究了它们的核辐射屏蔽行为和结构特性。根据 Bi2O3 的含量值,所研究的样品分别标记为 Bi0.0、Bi0.15、Bi0.30 和 Bi0.45。核屏蔽特性是通过 Phy-X/PSD 程序在 0.015 至 15 MeV 的光子能量范围内计算得出的。结果表明,质量衰减系数(MAC)从 4.2 cm2/g 到 88.5 cm2/g,线性衰减系数(LAC)从 8.99 cm-1 到 429.99 cm-1,半值层(HVL)从 0.077 cm 下降到 0.002 cm,十值层(TVL)从 1.570 cm 下降到 0.020 cm,平均自由路径(MFP)从 0.682 cm 下降到 0.009 cm。有效原子数(Zeff)从 12.9 到 77.5,有效电子密度(Neff)从 5.00 × 1023 到 8.60×1023 电子/克,原子和电子横截面(ACS 和 ECS)分别从 1.09 × 10-22 到 7.98 × 10-21 cm2/g,以及从 8.47 × 10-24 到 1.03 × 10-22 cm2/g。此外,还计算了制备样品的有效中子去除截面(ƩR)值。结果表明,氧化铋的加入改善了制备玻璃的核屏蔽性能,而且与混凝土玻璃和商用玻璃相比,Bi0.45 样品具有最佳的核屏蔽性能。
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EVALUATION OF NUCLEAR RADIATION SHIELDING BEHAVIOR AND STRUCTURE PROPERTIES OF NOVEL \(B_2O_3-Na_2O-K_2O-xBi_2O_3\) GLASSES
It was studied in this research the nuclear radiation shielding behavior and structure properties of the four glass samples which were composed of (80-x) B2O3-10Na2O-10K2O-xBi2O3 (x=0, 15, 30, 45 mol%) and were prepared using the melt-quenching technique. The studied samples were symbolized as Bi0.0, Bi0.15, Bi0.30, and Bi0.45 according to the Bi2O3 content values. The nuclear shielding properties have been calculated by the Phy-X/PSD program in the photon energy from 0.015 to 15 MeV. The results indicated that the values of mass attenuation coefficient (MAC) ranged from 4.2 to 88.5 cm2/g, linear attenuation coefficient (LAC) values ranged from 8.99 to 429.99 cm-1, half-value layer (HVL) values decreased from 0.077 to 0.002 cm, tenth value layer (TVL) values decreased from 1.570 to 0.020 cm, mean free path (MFP) values decreased from 0.682 to 0.009 cm, effective atomic number (Zeff) values ranged from 12.9 to 77.5, effective electron density (Neff) values ranged from 5.00 × 1023 to 8.60×1023 electrons/g, atomic and electron cross-sections (ACS and ECS) values ranged from 1.09 × 10-22 to 7.98 × 10-21 cm2/g and from 8.47 × 10-24 to 1.03 × 10-22 cm2/g respectively. The effective neutron removal cross-section (ƩR) values for prepared samples were also calculated. The results indicated that the addition of bismuth oxide leads to an improvement in the nuclear shielding properties of the prepared glass and showed that the sample Bi0.45 has the best nuclear shielding properties than concrete and commercial glasses.
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