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Technical Cross-cutting Issues for the Next Generation Safeguards Initiative's Spent Fuel Nondestructive Assay Project

机译:下一代保障计划的乏燃料无损检测项目的技术性跨领域问题

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Ever since there has been spent fuel (SF), researchers have made nondestructive assay (NDA) measurements of that fuel to learn about its content. In general these measurements have focused on the simplest signatures (passive photon and total neutron emission) and the analysis has often focused on diversion detection and on determining properties such as burnup (BU) and cooling time (CT). Because of shortcomings in current analysis methods, inspectorates and policy makers are interested in improving the state-of-the-art in SF NDA. For this reason the U.S. Department of Energy, through the Next Generation Safeguards Initiative (NGSI), targeted the determination of elemental Pu mass in SF as a technical goal. As part of this research effort, fourteen nondestructive assay techniques were studied. This wide range of techniques was selected to allow flexibility for the various needs of the safeguards inspectorates and to prepare for the likely integration of one or more techniques having complementary features. In the course of researching this broad range of NDA techniques, several cross-cutting issues were identified. This paper will describe some common issues and insights. In particular we will describe the following: (1) induced and non-induced fission-based techniques, (2) the role of neutron absorbers with emphasis on how these absorbers vary in SF as a function of initial enrichment, BU, and CT, as well as how some NDA techniques are more or less sensitive to neutron absorbers; and (3) the need to partition the measured signal among different isotopic sources and why this partitioning indicates which NDA techniques best integrate; (4) the importance of the "first generation" concept in the context of both diversion detection and in the context of determining Pu mass because the first generation indicates both the spatial and isotopic origins of the detected signal; and (5) the unique role played by ~(238)U and why in most cases it primarily acts as an amplifier of the signal generated by ~(235)U, ~(239)Pu, and ~(241)Pu.
机译:自从使用了乏燃料(SF)之后,研究人员就对该燃料进行了非破坏性测定(NDA)测量,以了解其含量。通常,这些测量集中在最简单的特征(无源光子和总中子发射)上,分析通常集中在转向检测和确定诸如燃耗(BU)和冷却时间(CT)之类的特性上。由于当前分析方法的缺陷,检查机构和政策制定者对改进SF NDA的最新技术感兴趣。因此,美国能源部通过下一代保障倡议(NGSI),将确定SF中的SF元素质量作为技术目标。作为这项研究工作的一部分,研究了14种无损检测技术。选择了广泛的技术,以便灵活地满足保障检查机构的各种需求,并为可能具有一种互补特征的一种或多种技术的整合做准备。在研究这种广泛的NDA技术的过程中,发现了一些跨领域的问题。本文将描述一些常见的问题和见解。特别是,我们将描述以下内容:(1)基于诱导和非诱导裂变的技术,(2)中子吸收剂的作用,重点在于这些吸收剂的SF随初始富集,BU和CT的变化而变化,以及某些NDA技术对中子吸收剂的敏感程度如何; (3)有必要在不同的同位素源之间划分被测信号,以及为什么这种划分表明哪种NDA技术最能整合? (4)“第一代”概念在转向检测和确定Pu质量的背景下的重要性,因为第一代指示检测到的信号的空间和同位素起源; (5)〜(238)U发挥的独特作用,以及为什么在大多数情况下它主要充当〜(235)U,〜(239)Pu和〜(241)Pu产生的信号的放大器。

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  • 来源
    《Journal of Nuclear Materials Management》 |2012年第3期|p.18-24|共7页
  • 作者单位

    Los Alamos National Laboratory, Los Alamos, New Mexico USA;

    Los Alamos National Laboratory, Los Alamos, New Mexico USA;

    Los Alamos National Laboratory, Los Alamos, New Mexico USA;

    Los Alamos National Laboratory, Los Alamos, New Mexico USA;

    Los Alamos National Laboratory, Los Alamos, New Mexico USA;

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