Assessment of Modeling Collimator Designs for Gamma-Ray Transmission of Uranium Oxide Spectrometry Using HPGe Detectors

Rasha Ali El-Tayebany, Hekmat Elbegawy
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Abstract

Many scientific domains use gamma-ray spectrometry, but non-destructive gamma scanning and gamma emission tomography of radioactive fuel in particular. In the experimental setting, a collimator is frequently employed to focus on a particular location of interest in the fuel. Predictive models for the transmitted gamma-ray intensity through the collimator are required for both the optimization of instrument design and the planning of measurement campaigns. Gamma-ray transport accuracy is frequently predicted using Monte Carlo radiation transport methods, but using these tools in low-efficiency experimental setups is challenging due to the lengthy computation times needed. This study focused on the full-energy peak intensity that was transmitted through several collimator designs, including rectangle and cylinder. The rate of photons arriving at a detector on the other side of the collimator was calculated for anisotropic source of SNM (U3O8). Some geometrical assumptions that depended on the source-to-collimator distance and collimator dimensions (length, radius or length, height, and width) were applied to achieve precise findings.
使用HPGe探测器的氧化铀光谱法伽马射线透射建模准直器设计评估
许多科学领域都使用伽马射线能谱法,但特别是对放射性燃料的非破坏性伽马扫描和伽马发射断层扫描。在实验环境中,准直仪经常用于聚焦燃料中感兴趣的特定位置。通过准直器传输的伽马射线强度的预测模型对于仪器设计的优化和测量活动的规划都是必需的。伽马射线输运精度通常使用蒙特卡罗辐射输运方法预测,但由于需要长时间的计算时间,在低效率的实验设置中使用这些工具是具有挑战性的。本文主要研究了几种准直器设计(矩形准直器和圆柱准直器)的全能峰值强度。计算了各向异性SNM (U3O8)源到达准直器另一侧探测器的光子速率。一些几何假设依赖于源到准直器的距离和准直器的尺寸(长度、半径或长度、高度和宽度),以获得精确的结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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