Design and manufacture of neutrons shield from composite materials

M. Ibrahim, K. Mahdi
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引用次数: 2

Abstract

Radiation protection principles may be specified within three parameters, limiting time, distance and shielding, the aim of this work is to make a shield for neutrons that we got from Am- Be source, the neutrons will be fast with energy of (5MeV), researchers designed exposure system that contain the source and the shield to be tested within three stages. The first stage was attenuated fast neutrons by composite material prepared from Epoxy as a matrix reinforced by Boron with different concentrations (0,5%,10%,12% and 15%) with thickness of (0.5)cm, then concentration 0f 12% was selected for test with different thickness of (0.5,1,1.5,2 and 2.5)cm, then 2cm was chose to start the second stage for the capture of thermal neutrons. The shield for thermal neutrons made from epoxy reinforced by cadmium at different concentration (0,10%,15%,20% and 25%) with thickness of (0.5)cm, then concentration 15% was chose to test with thickness of (0.5,1,1.5,2and 2.5)cm, the thickness of (1)cm. Finally a gamma shield made from Epoxy reinforced by lead with concentration of (0,10%,15%,20%and 25%) with thickness of (0.5)cm, then concentration 15% was choose to test with thickness of (0.5,1,1.5,2and 2.5)cm, the concentration of 15% with thickness of (1)cm was selected. So the shield is constructed in 3 layers of reinforced with Epoxy by Boron, Cadmium and Lead respectively, The linear absorption coefficient of neutrons for the Boron composite was 0.4212cm−1, for the composite cadmium was 0.1526cm−1 and for the lead composite was 0.126cm−1. The results show a good agreement with published data.Radiation protection principles may be specified within three parameters, limiting time, distance and shielding, the aim of this work is to make a shield for neutrons that we got from Am- Be source, the neutrons will be fast with energy of (5MeV), researchers designed exposure system that contain the source and the shield to be tested within three stages. The first stage was attenuated fast neutrons by composite material prepared from Epoxy as a matrix reinforced by Boron with different concentrations (0,5%,10%,12% and 15%) with thickness of (0.5)cm, then concentration 0f 12% was selected for test with different thickness of (0.5,1,1.5,2 and 2.5)cm, then 2cm was chose to start the second stage for the capture of thermal neutrons. The shield for thermal neutrons made from epoxy reinforced by cadmium at different concentration (0,10%,15%,20% and 25%) with thickness of (0.5)cm, then concentration 15% was chose to test with thickness of (0.5,1,1.5,2and 2.5)cm, the thickness of (1)cm. Finally a gamma shield ma...
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复合材料中子屏蔽的设计与制造
辐射防护原理可以限定在三个参数内,即限制时间、距离和屏蔽,本工作的目的是对来自Am- be源的中子进行屏蔽,中子将以(5MeV)的能量快速释放,研究人员设计了包含源和屏蔽的照射系统,分三个阶段进行测试。用不同浓度(0、5%、10%、12%和15%)、厚度(0.5)cm的环氧树脂为基体制备复合材料,对快中子进行衰减,然后选择浓度为0f - 12%的材料进行不同厚度(0.5、1、1.5、2和2.5)cm的试验,然后选择2cm开始第二阶段的热中子捕获。采用不同浓度(0、10%、15%、20%、25%)的镉增强环氧树脂制作热中子屏蔽膜,厚度分别为(0.5)cm和(15%)cm,厚度分别为(0.5、1、1.5、2、2.5)cm,厚度分别为(1)cm。最后用浓度分别为(0、10%、15%、20%和25%)、厚度分别为(0.5)cm的铅增强环氧树脂做屏蔽,然后选择浓度为15%、厚度分别为(0.5、1、1.5、2和2.5)cm的铅增强环氧树脂做屏蔽,再选择浓度为15%、厚度分别为(1)cm的铅增强环氧树脂做屏蔽。硼复合材料的中子线性吸收系数为0.4212cm−1,镉复合材料的中子线性吸收系数为0.1526cm−1,铅复合材料的中子线性吸收系数为0.126cm−1。结果与已发表的数据吻合较好。辐射防护原理可以限定在三个参数内,即限制时间、距离和屏蔽,本工作的目的是对来自Am- be源的中子进行屏蔽,中子将以(5MeV)的能量快速释放,研究人员设计了包含源和屏蔽的照射系统,分三个阶段进行测试。用不同浓度(0、5%、10%、12%和15%)、厚度(0.5)cm的环氧树脂为基体制备复合材料,对快中子进行衰减,然后选择浓度为0f - 12%的材料进行不同厚度(0.5、1、1.5、2和2.5)cm的试验,然后选择2cm开始第二阶段的热中子捕获。采用不同浓度(0、10%、15%、20%、25%)的镉增强环氧树脂制作热中子屏蔽膜,厚度分别为(0.5)cm和(15%)cm,厚度分别为(0.5、1、1.5、2、2.5)cm,厚度分别为(1)cm。终于有一个伽马屏蔽器了…
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