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首页> 外文会议>INMM annual meeting >Study of Performance of Portable Gamma-ray Spectroscopy Systems for 235U Isotopic Abundance Determination
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Study of Performance of Portable Gamma-ray Spectroscopy Systems for 235U Isotopic Abundance Determination

机译：便携式伽马射线光谱系统测定235U同位素丰度的性能研究

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The ~ 235U isotopic abundance determination using portable gamma-ray spectroscopy systems is widely used for nuclear material quantification and verification in the field. In nuclear safeguards, this technique constitutes a powerful tool for achieving immediate conclusions during inspections at nuclear facilities. The performance of some commercially available portable systems is being investigated by the Brazilian Safeguards Laboratory: a low resolution system composed by a 2”x2” NaI(Tl) crystal and a portable mini-multichannel analyzer model GBS-166; a low resolution compact system model Canberra Inspector-1000 with a 1.5”x 1.5” NaI(Tl) non-stabilized crystal model IPRON-1; and a high resolution system composed by a HPGe detector model Canberra GL1015R and a portable mini-multichannel analyzer model GBS-166. For data analysis, the spectra acquired with low resolution systems were analyzed by the NaIGEM® version 1.52a code. For the high resolution system, the MGAU® version 4.0 code was used. The purpose was to evaluate the performance of the systems in regards to the precision and biases for ~ 235U isotopic determination of typical nuclear material items found in nuclear facilities. In this study, the data acquisition and analysis was focused on measurements of low enriched 30B type UF6 cylinders that are routinely handled in a fuel fabrication plant. The performance results from each system were compared. Finally, the performance of each system for nuclear material verification activities in the field was discussed and compared to international performance standards.
机译：使用便携式伽马射线能谱系统测定〜235U同位素丰度，已广泛用于本领域中的核材料定量和验证。在核保障措施中，该技术是在核设施检查期间立即得出结论的有力工具。巴西保障实验室正在研究某些商用便携式系统的性能：一种由2英寸x2英寸NaI（Tl）晶体和便携式微型多通道分析仪GBS-166组成的低分辨率系统;具有1.5英寸x 1.5英寸NaI（Tl）非稳定晶体IPRON-1的低分辨率紧凑型系统堪培拉Inspector-1000;高分辨率系统由堪培拉GL1015R型HPGe检测器和GBS-166型便携式微型多通道分析仪组成。为了进行数据分析，使用NaIGEM®版本1.52a代码分析了低分辨率系统采集的光谱。对于高分辨率系统，使用了MGAU®4.0版代码。目的是就约235U同位素确定核设施中典型核材料项目的精度和偏差来评估系统的性能。在这项研究中，数据采集和分析的重点是在燃料制造厂中常规处理的低浓30B型UF6气缸的测量。比较了每个系统的性能结果。最后，讨论了在实地进行核材料核查活动的每个系统的性能，并将其与国际性能标准进行了比较。

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