Study of γ-ray Spectrum Measurement Analysis Algorithm of Radioactive Solid Waste Steel Boxes

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
Yurong Li, Lixia He, Jing Wen, Jiewen Shao
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引用次数: 0

Abstract

The steel boxes that contain radioactive solid wastes should be accurately identified and measured. On account of the uneven internal filling and radioactive distribution in the steel boxes that storing radioactive solid wastes, the non-destructive measurement analysis technique can be utilized to perform overall measurement of the wastes, which will not damage the steel boxes and produce secondary wastes. The γ-ray spectrum measurement analysis algorithm of radioactive solid waste steel boxes was set up by way of discrete treatment for γ-ray spectrum measurement analysis algorithm combined with the traditional CT principle in this paper, the progressive split voxel measurement method was applied to conduct discrete treatment for the radioactive solid waste steel boxes, with the influence of voxel interactions on detection efficiency was taken into consideration, the calibration model of detection efficiency was set up through Monte Carlo simulation combined with algebraic reconstruction technique, the inversion correction of efficiency for the physically coincident part of the detected voxel volume was achieved. The proposed algorithm was preliminarily applied on the analyze platform of steel boxes that storing FA-IV- type radioactive solid wastes, and the detection and verification on the standard radioactive source of known activities was also conducted, the findings revealed that the relative deviation between the reconstruction results and truth-value of radioactive activities in the steel boxes is less than 30%, which conformed to the expected results and the proposed algorithm can be popularized and applicated in the detection works in related to other.
放射性废钢箱γ射线谱测量分析算法研究
对装有放射性固体废物的钢箱应准确识别和测量。由于存放放射性固体废物的钢箱内部填充不均匀,放射性分布不均匀,可以利用无损测量分析技术对废物进行整体测量,不会损坏钢箱,产生二次废物。本文结合传统CT原理对γ射线光谱测量分析算法进行离散处理,建立放射性废钢箱γ射线光谱测量分析算法,采用逐级分割体素测量方法对放射性废钢箱进行离散处理,考虑体素相互作用对检测效率的影响。通过蒙特卡罗模拟结合代数重构技术建立了检测效率的标定模型,实现了对检测体素体物理重合部分效率的反演校正。将所提出的算法初步应用于存放FA-IV型放射性固体废物的钢箱分析平台,并对已知活度的标准放射源进行了检测与验证,结果表明,重建结果与钢箱放射性活度真值的相对偏差小于30%;实验结果符合预期,该算法可推广应用于其他相关的检测工作中。
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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