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The efficiency of a helium-3 neutron detector evaluated using MCNPX

机译:使用MCNPX评估的氦3中子探测器的效率

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A compact neutron source based on a piezoelectric transformer has been developed as part of an on-going research effort into radioisotope source replacements for oil-well logging and non-destructive testing applications. One of the key features that will dictate the viability of the device is the effective neutron yield produced during operation. A proportional counter that uses helium-3 as the active sensing material was used for the purpose of detecting neutrons. The detector response to neutrons depends upon the efficiency of the helium-3 proportional counter tube in conjunction with the solid angle subtended by the source and the detector, as well as the material system that surrounds the proportional counter. The coupled geometry effect and energy dependence of the detector efficiency make an analytical solution prone to error. Additionally, obtaining a calibrated neutron source that mimics the size and desired activity of the piezoelectric transformer-based source was not in the scope of the research. Consequently, a numerical model of the neutron source and detector was developed and subjected to Monte Carlo analysis using MCNPX using neutrons as the source particles. A sensitivity analysis of the detector position and orientation was used to determine the optimal location for high-sensitivity neutron counting.
机译:作为针对油井测井和非破坏性测试应用的放射性同位素源替代品正在进行的研究工作的一部分,已经开发了一种基于压电变压器的紧凑型中子源。决定装置生存能力的关键特征之一是在操作过程中产生的有效中子产率。为了检测中子,使用了以氦3作为活性传感材料的比例计数器。探测器对中子的响应取决于氦3比例计数管的效率,以及源和探测器所包围的立体角,以及包围比例计数器的材料系统。耦合的几何效应和检测器效率的能量依赖性使得分析解决方案易于出错。另外,获得一种模拟中子源,该中子源模仿压电变压器基源的大小和所需的活动,不在研究范围之内。因此,开发了中子源和探测器的数值模型,并使用MCNPX将中子作为源粒子,进行了蒙特卡洛分析。使用探测器位置和方向的灵敏度分析来确定高灵敏度中子计数的最佳位置。

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