首页> 外文会议>Annual meeting of the Institute of Nuclear Materials Management >A SECOND LOOK AT NEUTRON RESONANCE TRANSMISSION ANALYSIS AS A SPENT FUEL NDA TECHNIQUE
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A SECOND LOOK AT NEUTRON RESONANCE TRANSMISSION ANALYSIS AS A SPENT FUEL NDA TECHNIQUE

机译:中子共振传输分析的第二次发现是一种燃料NDA技术

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Neutron Resonance Transmission Analysis (NRTA) is measurement technique capable of quantifying plutonium in spent fuel. Having first been explored in the mid-1970s for the analysis of individual spent-fuel pins, a second look is now underway to investigate the suitability of the NRTA technique for assaying complete spent nuclear fuel assemblies using advanced simulation and modeling methods. The technique is similar to neutron time-of-flight methods used for neutron cross-section measurements but operates over only the narrow 0.1-20 eV range where strong, distinguishable resonances exist for both the plutonium (~(239,240,241,242)Pu) and uranium (~(235,236,238)U) isotopes of interest in spent fuel. Additionally, in this energy range resonances exists for six important fission products (~(99)Tc, ~(103)Rh, ~(131)Xe, ~(133)Cs, ~(145)Nd, and ~(152)Sm) which provide additional information to support spent fuel plutonium assay determinations. Initial modeling shows excellent agreement with previously published experimental data for measurements of individual spent-fuel pins where plutonium assays were demonstrated to have a precision of 2-4%. Within the simulation and modeling analyses of this project scoping studies have explored fourteen different aspects of the technique including the neutron source, drift tube configurations, and gross neutron transmission as well as the impacts of fuel burn up, cooling time, and fission-product interferences. These results show that NRTA may be a very capable experimental technique for spent-fuel assay measurements. The results suggest sufficient transmission strength and signal differentiability is possible for assays through up to 8 pins. For an 8-pin assay (looking at an assembly diagonally), 64% of the pins in a typical 17×17 array of a pressurized water reactor fuel assembly can be part of a complete transmission assay measurement with high precision. Analysis of rows with up to 12 pins may also be feasible but with diminished precision. Preliminary analysis of an NRTA simulation has demonstrated the simplicity of the technique. This work is part of a larger effort sponsored by the Next Generation Safeguards Initiative to develop an integrated instrument, comprised of individual nondestructive assay techniques with complementary features, that is fully capable of determining Pu mass in spent fuel assemblies.
机译:中子共振传输分析(NRTA)是一种能够量化乏燃料中p的测量技术。在1970年代中期首次对单个乏燃料销的分析进行了研究之后,现在正在进行第二次研究,以研究NRTA技术是否适用于使用先进的模拟和建模方法测定完整的乏核燃料组件的适用性。该技术类似于用于中子截面测量的中子飞行时间方法,但是仅在狭窄的0.1-20 eV范围内运行,其中where(〜(239,240,241,242)Pu)和铀( 〜(235,236,238)U)乏燃料中感兴趣的同位素。此外,在此能量范围内,六个重要裂变产物(〜(99)Tc,〜(103)Rh,〜(131)Xe,〜(133)Cs,〜(145)Nd和〜(152)Sm)存在共振),这些信息可提供其他信息以支持乏燃料p测定法的确定。初始模型显示出与先前发布的用于测量单个乏燃料销的实验数据极好的一致性,其中p测定的精确度被证明为2-4%。在该项目的模拟和模型分析中,范围研究已经研究了该技术的十四个不同方面,包括中子源,漂移管构型和中子传输总量,以及燃料燃烧,冷却时间和裂变产物干扰的影响。 。这些结果表明,NRTA可能是一种用于乏燃料分析测量的非常有能力的实验技术。结果表明,对于多达8个引脚的测定,足够的传输强度和信号可区分性是可能的。对于8针测定(对角线观察组件),压水堆燃料组件的典型17×17阵列中的64%的针可以高精度地进行完整的透射测定的一部分。最多分析12个引脚的行也是可行的,但精度降低。 NRTA模拟的初步分析证明了该技术的简便性。这项工作是“下一代保障计划”(Next Generation Safeguards)赞助的一项更大努力的一部分,该计划旨在开发一种集成仪器,该仪器由具有互补功能的各个非破坏性测定技术组成,完全能够确定乏燃料组件中的Pu质量。

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