Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
复制标题
使用蒙特卡罗代码提高伽马能谱仪的分析性能以精确测量铀样品
DOI：
10.1016/j.rinp.2020.103145
复制
发表时间：
2020
影响因子：
5.3
通讯作者：
M. Hazzaa
中科院分区：
文献类型：
--
作者：
K. Gawad;Zhang Zhijian;M. Hazzaa
铀的定量和测量是核技术中所有使用过的核材料的一项重要任务。本工作着重于基于估算技术的γ谱仪性能的改进和优化。优化进行了准确的铀样品表征的基础上使用蒙特卡罗代码（MC）建模。使用的样品均经过认证，为核材料。使用锗检测器基于非破坏性方法测定测量质量。使用初始MC模型的基础上的标称探测器参数，宽的测量和模拟结果之间的差异高达55%。因此，计算的铀质量与参考值相比有高达35%的相对变化。为了克服这种变化，MC模型是通过优化的检测器尺寸。MC优化模型的计算结果与标准值吻合较好，误差小于2%。
Uranium quantification and measurements represent a vital task for all used nuclear materials in nuclear technology. This work emphasizes the improvements and optimization of gamma spectrometer performance based on estimation techniques. The optimization was carried out for accurate uranium samples characterization based on modeling using the Monte Carlo code (MC). The used samples are certified and nuclear materials. The measured masses were determined based on non-destructive method using a germanium detector. Using the initial MC model based on the nominal detector parameters, wide discrepancies up to 55% between measured and simulated results were obtained. Consequently, the calculated uranium masses have a high relatively variations up to 35% than the reference values. To overcome such variations, the MC model was developed through optimization of the detector dimensions. A good agreement between the results of the MC optimized model and the certified values has been obtained with a variation less than 2%.