HR GRS-HPGe 作为无损检测方法,用于量化二氧化铀燃料生产设施工艺流样品中的铀和铀 235 含量

IF 1.4 3区 化学 Q4 CHEMISTRY, INORGANIC & NUCLEAR Radiochimica Acta Pub Date : 2023-12-11 DOI:10.1515/ract-2023-0186
Yarasi Balaji Rao, Vinod K. Ray, Putta V. Nagendra Kumar, Dinesh Srivastava
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引用次数: 0

摘要

铀浓度和铀同位素含量是任何核燃料制造设施的两个重要和关键参数。本研究的重点是利用高分辨率伽马射线光谱(HR-GRS)技术和 HPGe 探测器来测定铀工艺流样品中的铀和 235U 含量。开展这项工作的目的是为生产设施提供快速的分析反馈,并最大限度地减少分析废物的产生。这些都是任何工业实验室的重要要求,因为生产设施附带的分析负荷很高。本文介绍了一种简单的无损检测(NDT)方法,利用 HR-GRS 技术和高纯锗(HPGe)检测器对从二氧化铀燃料生产设施收到的样品中的铀和 235U 含量进行量化。235U 的 185.7 keV 线用于定量含 1 克/升至 600 克/升铀的工艺溶液中的铀,包括水溶液和有机工艺流溶液。结果与戴维斯和格雷方法进行了比较。此外,还研究了与 238U 子产物发射的伽马射线以及铀的自诱导或自激发 X 射线荧光线有关的限制。多组铀分析(MGAU)软件代码用于测量各种样品中 235U 的含量。获得的结果与热电离质谱仪(TIMS)的结果进行了比较。
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HR GRS-HPGe as NDT method for quantification of uranium and U235 content in process stream samples from UO2 fuel production facilities
Uranium concentration and uranium isotopic content are two important and critical parameters for any nuclear fuel fabrication facilities. In the present study emphasis has been given on the usage of high resolution gamma ray spectrometric (HR-GRS) technique with HPGe detector for the determination of uranium and 235U content in uranium process stream samples. The work has been carried out with an aim to give quick analytical feedback to production facility and also to minimize the generation of analytical waste. These are important requirements for any industrial lab with high analytical load attached to production facility. In this paper a simple and a non-destructive testing (NDT) method has been described for quantification of uranium and 235U content in samples received from UO2 fuel production facilities using HR-GRS technique with high purity germanium (HPGe) detector. A 185.7 keV line of 235U has been used for quantification of uranium in process solutions containing 1 g/L to 600 g/L of uranium covering both aqueous and organic process stream solutions. The results have been compared with that of Davies and Gray method. The limitations associated with gamma ray emitted from daughter products of 238U and self-induced or self-excited X-ray fluorescence lines of uranium have also been studied. Multi Group Analysis of Uranium (MGAU) software code has been used for measurement of 235U content in variety of samples. The results obtained are compared with that of results by thermal ionization mass spectrometer (TIMS).
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来源期刊
Radiochimica Acta
Radiochimica Acta 化学-核科学技术
CiteScore
2.90
自引率
16.70%
发文量
78
审稿时长
6 months
期刊介绍: Radiochimica Acta publishes manuscripts encompassing chemical aspects of nuclear science and technology.
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