黄铜合金和碳化硼增强混凝土试样的力学和辐射屏蔽特性研究。

IF 1.6 3区 工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR Applied Radiation and Isotopes Pub Date : 2024-12-15 DOI:10.1016/j.apradiso.2024.111641
İ. Erkoyuncu , İ. Demirkol , F. Akman , M.R. Kaçal , H. Polat , K. Dilsiz
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引用次数: 0

摘要

研究了水泥质量为10%、20%、30%、40%和50%的黄铜合金对混凝土样品屏蔽γ辐射性能的影响。为了测试样品的γ屏蔽性能,通过实验、理论和Monte Carlo模拟(GEANT4和FLUKA),确定了样品的质量和线性衰减系数、半值层和十值层、有效原子序数和辐射防护效率参数。这些研究是在11种不同的伽马能量下进行的,从59.5到1332.5 keV,从22Na, 60Co, 133Ba, 137Cs和241Am放射源发射。结果表明,随着黄铜合金含量的增加,试样的屏蔽性能有所提高,其中黄铜合金含量为50%的试样屏蔽效果最好。通过添加5%、10%、15%和20%碳化硼(B4C),研究了50%黄铜合金增强试样的中子屏蔽性能。利用GEANT4和FLUKA模拟程序对B4C掺加混凝土试样中子屏蔽性能的重要参数中子渗透率进行了研究。对于代号为P0、P50、P50B5、P50B10、P50B15和P50B20的混凝土,用GEANT4获得的宏观截面总结果分别为2.0290、2.0324、2.0343、2.0346、2.0361和2.0367 cm-1,用FLUKA获得的结果分别为2.0287、2.0322、2.0337、2.0342、2.0357和2.0362 cm-1。因此,含20% B4C的样品是屏蔽中子辐射效果最好的样品。除了测试样品的辐射屏蔽性能外,还测试了样品的抗压强度、施密特表面硬度、超声脉冲速度等力学性能。
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A study on the mechanical and radiation shielding characteristics of concrete samples reinforced with brass alloy and boron carbide
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 22Na, 60Co, 133Ba, 137Cs and 241Am 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 (B4C). The neutron permeability, which is an important parameter in terms of the neutron shielding performance of B4C 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% B4C 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.
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来源期刊
Applied Radiation and Isotopes
Applied Radiation and Isotopes 工程技术-核科学技术
CiteScore
3.00
自引率
12.50%
发文量
406
审稿时长
13.5 months
期刊介绍: Applied Radiation and Isotopes provides a high quality medium for the publication of substantial, original and scientific and technological papers on the development and peaceful application of nuclear, radiation and radionuclide techniques in chemistry, physics, biochemistry, biology, medicine, security, engineering and in the earth, planetary and environmental sciences, all including dosimetry. Nuclear techniques are defined in the broadest sense and both experimental and theoretical papers are welcome. They include the development and use of α- and β-particles, X-rays and γ-rays, neutrons and other nuclear particles and radiations from all sources, including radionuclides, synchrotron sources, cyclotrons and reactors and from the natural environment. The journal aims to publish papers with significance to an international audience, containing substantial novelty and scientific impact. The Editors reserve the rights to reject, with or without external review, papers that do not meet these criteria. Papers dealing with radiation processing, i.e., where radiation is used to bring about a biological, chemical or physical change in a material, should be directed to our sister journal Radiation Physics and Chemistry.
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