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Total gamma count rate analysis method for characterizing transuranic waste.

机译:用于表征超铀废物的总伽马计数率分析方法。

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摘要

Gamma-ray spectrometry systems are used in a variety of applications. However, the ability to characterize transuranic waste with a gamma spectroscopy system and have a minimum detection limit of less than 10 nCi/g of transuranic activity concentration is difficult with conventional photopeak analysis routines. The objective of this research is to determine the viability of the integral count method for characterizing transuranic waste and achieve a minimum detection limit of 10 nCi/g of transuranic activity concentration. The Idaho Cleanup Project sponsored the total gamma count rate research project to determine if this method could be used in waste retrieval operations at the Idaho National Laboratory Site.;The total gamma count rate is a measure of the total number of gamma interactions that produce energetic electrons or positrons seen in a detector. The interactions are photoelectric effect, Compton scattering, electron-positron pair production, and multiple gamma-ray scattering events.;A two-tier approach was used in this research project: (1) assess real waste data previously collected at the Idaho National Laboratory Site and (2) use simulated transuranic waste containers. Both tiers were designed to determine if the total gamma count rate analysis method could characterize transuranic waste for disposal and if a nominal minimum detection limit of 10 nCi/g of transuranic activity concentration could be obtained. The real waste assay analyses targeted filters, graphite, organic sludge, and inorganic sludge while the simulated transuranic waste containers targeted filters, graphite, organic sludge, and inorganic sludge, and sand.;The total gamma count rate analysis method results for real waste assay data and the results for simulated waste assay data were linear within statistical accuracy with respect to the expected or known value thereby indicating applicability to characterize transuranic waste for disposal.;Using Currie's formula to determine minimum detection limits, the predicted MDLs were less than 10 nCi/g transuranic activity concentration for each real waste matrix and for the simulated transuranic waste containers.;This research demonstrated that the total gamma count rate analysis method can be used for characterization of transuranic waste for disposal purposes and achieve a minimum detection limit of 10 nCi/g of transuranic activity concentration.
机译:伽马射线光谱分析系统被用于多种应用中。但是,使用常规的光电峰分析程序很难用γ光谱系统表征超铀废物,并且其最小检出限小于10 nCi / g超铀活性浓度。这项研究的目的是确定用于表征超铀废料的积分计数方法的可行性,并实现最低检出限为10 nCi / g超铀活性浓度。爱达荷州清洁项目资助了总伽玛计数率研究项目,以确定该方法是否可以在爱达荷州国家实验室站点的废物回收操作中使用。总伽玛计数率是产生能量的伽玛相互作用总数的量度。在探测器中看到的电子或正电子。这些相互作用是光电效应,康普顿散射,电子-正电子对产生和多个伽马射线散射事件。;本研究项目使用了两层方法:(1)评估先前在爱达荷州国家实验室收集的真实废物数据场地和(2)使用模拟的超铀废物容器。设计这两个层次都是为了确定总伽马计数率分析方法是否可以表征超铀废物的处置方式,以及是否可以获得标称最小检出限为10 nCi / g超铀活性浓度。真实废物分析可分析目标过滤器,石墨,有机污泥和无机污泥,而模拟超铀废物容器则可分析目标过滤器,石墨,有机污泥,无机污泥和沙子;总γ计数率分析方法结果可用于真实废物分析数据和模拟废物分析数据的结果在相对于预期或已知值的统计精度范围内是线性的,从而表明适用于表征超铀废物进行处置。;使用Currie公式确定最小检出限,预测的MDL小于10 nCi / g每个实际废物基质和模拟的超铀废物容器的超铀活动浓度。;该研究表明,总伽马计数率分析方法可用于表征超铀废物以进行处置,并达到10 nCi的最低检测限/ g超铀活性浓度。

著录项

  • 作者

    Hoffman, Cecilia R.;

  • 作者单位

    Idaho State University.;

  • 授予单位 Idaho State University.;
  • 学科 Nuclear physics.
  • 学位 Ph.D.
  • 年度 2006
  • 页码 224 p.
  • 总页数 224
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 宗教史、宗教地理;
  • 关键词

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