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Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples
Results in Physics ( IF 4.4 ) Pub Date : 2020-05-07 , DOI: 10.1016/j.rinp.2020.103145
K. Abd El Gawad , Zhang Zhijian , M.H. Hazzaa

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 %.



中文翻译:

使用蒙特卡洛代码提高γ光谱仪的分析性能,以准确测量铀样品

铀的量化和测量是核技术中所有已用核材料的一项至关重要的任务。这项工作着重于基于估计技术的伽马能谱仪性能的改进和优化。基于蒙特卡罗代码(MC)的建模,对铀样品进行了准确的表征以进行优化。所用样品均为经过认证的核材料。使用锗检测器基于非破坏性方法来确定测量的质量。使用基于标称检测器参数的初始MC模型,在测量结果和模拟结果之间的差异高达55%。因此,计算出的铀质量比参考值高出35%。为了克服这种变化,MC模型是通过优化探测器尺寸而开发的。MC优化模型的结果与认证值之间的一致性很好,偏差小于2%。

更新日期:2020-05-07
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