Γ-Ray光谱定量核材料含率检测效率拟合方法研究

Yurong Li, Sijia Wang, Jing Wang, Lixia He
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引用次数: 0

摘要

“滞留物”是指贮存在处理设施的设备、容器、管道等中的核材料。核材料控制和核算要求对核材料在制品滞留情况进行监测。Holdup对于指示设施运行状态、关键辐射安全状态等非常有用。核材料含率的定量分析采用破坏性分析方法较为困难。因此,现场和在线检测的无损分析(NDA)技术是最适合实际情况的含率定量分析方法。为了得到γ射线光谱定量检测核物质含率的效率。本文采用蒙特卡罗仿真与实验相结合的方法,对本征检测效率、几何检测效率和自吸收衰减校正方法进行了研究。采用三维拟合和最小二乘拟合方法,简化了核设施生产线模拟管道系统中核材料含率的分布。实验结果表明,申报值与实测值的偏差小于30%。相对于国家核保障监督的要求和设施运行的需要,采用γ射线能谱法定量研究核材料含率的检测效率拟合方法是可行的。它还可广泛用于辐射剂量监测、退役源项目调查等方面提供相关数据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Detection Efficiency Fitting Method Research by Γ-Ray Spectroscopy for Quantitative Nuclear Material Holdup
The term “holdup” refers to nuclear material that has been deposited in the processing facility’s equipment, containers, pipelines, etc. Nuclear material control and accounting require the monitoring of nuclear material holdup in process. Holdup is useful for indicating the state of facility operations, critical radiation safety status, and so on. It is more difficulty to quantitative analyzed nuclear material holdup by destructive analysis method. So non-destructive analysis (NDA) technology for in-situ and on-line measurement satisfied to the actual situation are the most recommended nominator for holdup quantitative analysis. In order to get the detection efficiency of γ-ray spectroscopy for quantitative nuclear material holdup. The intrinsic detection efficiency, geometric detection efficiency, and self-absorption attenuation correction methods are researched in this paper by combining Monte Carlo simulation and experiment. Three-dimensional and the least square fitting methods, and the distribution of the nuclear material holdup in the simulation pipeline system of nuclear facilities’ production line is simplified. Resulted to the experiment, the deviation between declared and the measured value is less than 30%. Compared with the requirements of national nuclear safeguards supervision and the needs of facility operation, the detection efficiency fitting method research by γ-ray spectroscopy for quantitative nuclear material holdup is achievable. It also can be widely used to provide relevant data in radiation dose monitoring, decommissioning source item investigation, and so on.
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