不同B4C颗粒增强Al-Cu基复合材料辐射衰减性能研究

U. Gökmen, Zübeyde Özkan, Leili Eslam Jamalgolzari, S. Ocak
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引用次数: 1

摘要

近年来,b4c粒子增强铝基复合材料因其中子吸收性和轻量化而被广泛应用于γ和中子屏蔽。本文利用XCOM平台理论计算了b4c (5- 15wt %)颗粒增强Alumix 13和Alumix 231(含Cu和Mg等特殊合金元素)铝基复合材料在80 keV、356 keV、137Cs (662 keV)、60Co (1173 keV、1332 keV)和2000 keV(高能)γ能量下的线性和质量衰减系数。分别评价了B4C (5-15 wt%)颗粒增强Alumix 13和Alumix 231基复合材料除总衰减系数外的对产生、相干散射、光电吸收和非相干散射过程。另一方面,还计算了半值厚度(HVL)值和十分之一厚度(TVL)值,以评估该材料的辐射屏蔽效果,不包括伽马射线输运理论中经常使用的相干散射值以及总衰减系数。理论计算了Al复合材料在80 keV、356 keV、137Cs (662 keV)、60Co (1173 keV、1332 keV)和2000 keV(高能)下的γ衰减曲线,并绘制了b4c (5-15 wt%)颗粒增强Alumix 13和Alumix 231基复合材料的γ衰减曲线。在此基础上,对该材料的辐射衰减性能和屏蔽性能进行了研究。因此,本研究具有多方面的原创性,其研究成果不仅可以应用于核技术,还可以应用于纳米技术、空间技术等其他技术。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Investigation of Radiation Attenuation Properties of Al-Cu Matrix Composites Reinforced by Different Amount of B4C Particles
In recent years, B 4 C particle reinforced Al matrix composite materials have been excessively used for gamma and neutron shielding regarding their neutron absorption and lightweight. In this paper, linear and mass attenuation coefficients using 80 keV, 356 keV, 137Cs (662 keV), 60Co (1173 keV,1332 keV) and 2000 keV(high energy) gamma energies for B 4 C (5-15 wt%) particle-reinforced Alumix 13 and Alumix 231 (which contains special alloy elements such as Cu and Mg) aluminum matrix composites were theoretically calculated with XCOM platform. Pair production, coherent scattering, photoelectric absorption and incoherent scattering processes besides the total attenuation coefficients for B4C (5-15 wt%) particle-reinforced Alumix 13 and Alumix 231 matrix composite materials were evaluated separately. On the other hand, half-value thickness (HVL) values and one-tenth thickness values (TVL) were also calculated to evaluate the radiation shielding effectiveness of this material excluding coherent scattering values that are frequently used in gamma ray transport theory as well as the total attenuation coefficients. Gamma attenuation curves for Al composite materials against 80 keV, 356 keV, 137Cs (662 keV), 60Co (1173 keV, 1332 keV) and 2000 keV (high energy) gamma energies were theoretically calculated and plotted for B 4 C (5-15 wt%) particle-reinforced Alumix 13 and Alumix 231 matrix composite materials. According to the obtained results for this material, radiation attenuation properties and the ability of shielding of materials were investigated. Therefore, this study is original from a variety of aspects, and its results may be used not only in nuclear technology but also in other technologies such as nano and space technology.
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