Erkoyuncu I, Demirkol I, Akman F, Kaçal M R, Polat H, Dilsiz K
Bingöl University, Faculty of Arts and Science, Department of Physics, 12000, Bingöl, Türkiye.
Bingöl University, Faculty of Arts and Science, Department of Physics, 12000, Bingöl, Türkiye.
Appl Radiat Isot. 2025 Mar;217:111641. doi: 10.1016/j.apradiso.2024.111641. Epub 2024 Dec 15.
In this study, the gamma radiation shielding properties of concrete samples reinforced with 10%, 20%, 30%, 40% and 50% of the cement weight of brass alloy were investigated. To test gamma shielding performance of the samples, mass and linear attenuation coefficients, half and tenth value layers, effective atomic number and radiation protection efficiency parameters were determined experimentally, theoretically and Monte Carlo simulations (GEANT4 and FLUKA). The studies were performed at 11 different gamma energies that range from 59.5 to 1332.5 keV emitted from Na, Co, Ba, Cs and Am radioactive sources. The obtained results showed that the gamma shielding property of the samples increases with increasing brass alloy amount, and the sample reinforced with 50% brass alloy was the most effective one to shield gamma radiation. Neutron shielding properties of the sample reinforced with 50% brass alloy were therefore investigated by adding 5%, 10%, 15% and 20% boron carbide (BC). The neutron permeability, which is an important parameter in terms of the neutron shielding performance of BC added concrete samples, was investigated by using GEANT4 and FLUKA simulation programs. While the total macroscopic cross section results obtained with GEANT4 for concretes coded as P0, P50, P50B5, P50B10, P50B15 and P50B20 are 2.0290, 2.0324, 2.0343, 2.0346, 2.0361 and 2.0367 cm-1, respectively, the results obtained with FLUKA are 2.0287, 2.0322, 2.0337, 2.0342, 2.0357 and 2.0362 cm-1, respectively. Therefore, the sample containing 20% BC is the sample that best shields neutron radiation. In addition to the radiation shielding properties of the produced samples, the mechanical properties such as compressive strength, Schmidt surface hardness, ultrasound pulse velocity were also tested in terms of usability.
在本研究中，对用占水泥重量10%、20%、30%、40%和50%的黄铜合金增强的混凝土样品的γ辐射屏蔽性能进行了研究。为测试样品的γ屏蔽性能，通过实验、理论计算以及蒙特卡罗模拟（GEANT4和FLUKA）确定了质量衰减系数、线性衰减系数、半值层、十分之一值层、有效原子序数和辐射防护效率参数。研究在11种不同的γ能量下进行，这些能量范围为59.5至1332.5 keV，由钠、钴、钡、铯和镅放射性源发射。所得结果表明，样品的γ屏蔽性能随黄铜合金含量的增加而提高，用50%黄铜合金增强的样品对γ辐射的屏蔽效果最为显著。因此，通过添加5%、10%、15%和20%的碳化硼（BC），对用50%黄铜合金增强的样品的中子屏蔽性能进行了研究。利用GEANT4和FLUKA模拟程序研究了添加BC的混凝土样品中子屏蔽性能方面的一个重要参数——中子渗透率。对于编码为P0、P50、P50B5、P50B10、P50B15和P50B20的混凝土，用GEANT4得到的总宏观截面结果分别为2.0290、2.0324、2.0343、2.0346、2.0361和2.0367 cm⁻¹，用FLUKA得到的结果分别为2.0287、2.0322、2.0337、2.0342、2.0357和2.0362 cm⁻¹。因此，含20% BC的样品是中子辐射屏蔽效果最佳的样品。除了所制备样品的辐射屏蔽性能外，还从可用性角度测试了抗压强度、施密特表面硬度、超声脉冲速度等力学性能。
