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A SECOND LOOK AT NEUTRON RESONANCE TRANSMISSION ANALYSIS AS A SPENT FUEL NDA TECHNIQUE

机译:第二种外观中子共振传输分析作为花费燃料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:中子共振传递分析(NRTA)是能够在燃料中量化钚的测量技术。首先在20世纪70年代中期探讨了用于分析个体花燃料销的分析,现在正在进行第二种外观来研究NRTA技术采用先进的模拟和建模方法测定完整的核燃料组件的适用性。该技术类似于用于中子横截面测量的中子飞行时间,但仅在钚(〜(239,240,241,242)PU)和铀( 〜(235,236,238)U)对燃料的感兴趣的同位素。另外,在这种能量范围内存在六种重要裂变产物(〜(99)Tc,〜(103)rh,〜(131)xe,〜(133)Cs,〜(145)Nd,〜(152)Sm )提供额外信息以支持花费燃料钚测定确定。初始建模显示出优异的一致性与先前公布的实验数据,用于测量用于钚测定的单个花燃料销的测量,其中钚测定具有2-4%的精度。在该项目的仿真和建模分析中,该项目的研究已经探讨了本技术的十四个不同方面,包括中子源,漂移管配置和总体中子传输以及燃料烧伤,冷却时间和裂变 - 产品干扰的影响。这些结果表明,NRTA可以是用于废燃料测定测量的非常有能力的实验技术。结果表明,通过多达8个引脚可以进行足够的传输强度和信号可分性。对于8针测定(观察对角线的组件),典型的17×17型阵列的64%的加压水反应堆燃料组件可以是具有高精度的完全传输测定测量的一部分。分析最多12个引脚的行也可能是可行的,但精度减少。 NRTA模拟的初步分析表明了该技术的简单性。这项工作是由下一代保障计划开发一种具有互补特征的单独无损测定技术的综合仪器提供的较大努力的一部分,该技术完全能够在花费燃料组件中确定PU质量。

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