首页> 外文会议>Annual meeting of the Institute of Nuclear Materials Management >A Gamma Ray Scanning Approach to Quantify Spent Fuel Cask Radionuclide Contents
【24h】

A Gamma Ray Scanning Approach to Quantify Spent Fuel Cask Radionuclide Contents

机译:伽马射线扫描法量化乏燃料桶中放射性核素的含量

获取原文

摘要

The International Atomic Energy Agency (IAEA) has outlined a need to develop methods of allowing re-verification of LWR spent fuel stored in dry storage casks without the need of a reference baseline measurement. Some scanning methods have been developed, but improvements can be made to readily provide required data for spent fuel cask verification. The scanning process should be conditioned to both confirm the contents and detect any changes due to container/contents degradation or unauthorized removal or tampering. Savannah River National Laboratory and The University of Tennessee are exploring a new method of engineering a high efficiency, cost effective detection system, capable of meeting the above defined requirements in a variety of environmental situations. An array of Nal(Tl) detectors, arranged to form a "line scan" along with a matching array of "honeycomb" collimators provide a precisely defined field of view with minimal degradation of intrinsic detection efficiency and with significant scatter rejection. Scanning methods are adapted to net optimum detection efficiency of the combined system. In this work, and with differing detectors, a series of experimental demonstrations are performed that map system spatial performance and counting capability before actual spent fuel cask scans are performed. The data are evaluated to demonstrate the prompt ability to identify missing fuel rods or other content abnormalities. To also record and assess cask tampering, the cask is externally examined utilizing FTIR hyper spectral and other imaging/sensing approaches. This provides dated records and indications of external abnormalities (surface deposits, smears, contaminants, corrosion) attributable to normal degradation or to tampering. This paper will describe the actual gathering of data in both an experimental climate and from an actual spent fuel dry storage cask, and how an evaluation may be performed by an IAEA facility inspector attempting to draw an independent safeguards conclusion concerning the status of the special nuclear material.
机译:国际原子能机构(IAEA)概述了需要开发的方法,这些方法允许重新验证存储在干燥储罐中的轻水堆乏燃料,而无需进行基准基准测量。已经开发了一些扫描方法,但是可以进行改进以容易地提供用于乏燃料桶验证的所需数据。应当对扫描过程进行调节,以确认内容物并检测由于容器/内容物质量下降或未经授权的拆卸或篡改而引起的任何变化。萨凡纳河国家实验室和田纳西大学正在探索一种工程设计高效,经济高效的检测系统的新方法,该方法能够在各种环境条件下满足上述定义的要求。布置成形成“线扫描”的Nal(T1)检测器阵列以及匹配的“蜂窝”准直器阵列提供了精确定义的视野,而固有检测效率的降级最小且散射抑制显着。扫描方法适用于组合系统的最佳检测效率。在这项工作中,并使用不同的检测器,进行了一系列实验演示,它们在执行实际的乏燃料桶扫描之前,绘制了系统的空间性能和计数能力。对数据进行评估以证明能够迅速识别丢失的燃料棒或其他内容异常。为了也记录和评估桶的篡改,可使用FTIR高光谱和其他成像/传感方法从外部检查桶。这提供了过时的记录和指示,这些异常是由于正常降解或篡改引起的外部异常(表面沉积物,污迹,污染物,腐蚀)。本文将描述在实验性气候和实际乏燃料干燥存储桶中的实际数据收集,以及国际原子能机构设施检查员可能如何进行评估,以试图得出有关特殊核武器状态的独立保障结论。材料。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号