首页> 外文期刊>Nuclear Instruments & Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment >Nondestructive measurements of residual ~(235)U mass of Israeli Research Reactor-1 fuel using the Advanced Experimental Fuel Counter
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Nondestructive measurements of residual ~(235)U mass of Israeli Research Reactor-1 fuel using the Advanced Experimental Fuel Counter

机译:使用高级实验燃料计数器对以色列Research Reactor-1燃料的〜(235)U残留量进行无损测量

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In 2018, a measurement campaign took place with participants from Los Alamos National Laboratory (LANL), the Nuclear Research Centre-Negev (NRCN) and Soreq Nuclear Research Center (SNRC) at the Israeli Research Reactor-1 (IRR-1) in which 14 of the reactor's used fuel assemblies (FAs) with varied amount of depletion were measured with the nondestructive assay instrument Advanced Experimental Fuel Counter (AEFC). Designed for safeguards purposes, the AEFC measures both neutrons emitted from the FA (passive neutrons) and fission neutrons induced by an external neutron source (in this experiment, ~(252)Cf). Signals recorded with the AEFC include total neutron count rates (Singles), time-correlated neutron count rates (Doubles), and total gamma-ray count rates. The ~(235)U content of the FAs was previously assessed by two independent methods: (1) measurement of the transparency of the FA to low-energy gamma rays from an activated rhenium source (rhenium gamma transmission, or the RGT method) and (2) calculation of the ~30-year burnup history of the core using detailed three-dimensional Monte-Carlo core depletion calculations. The results from the FAs that had been measured via the RGT method were used to construct the calibration curves, which translate the AEFC count rates to ~(235)U mass. Then, the calibration was evaluated using AEFC measurements of six additional FAs that were not measured via the RGT method. From the results, it was determined the Doubles calibration curve was more reliable than that of the Singles and follows a simple second-order polynomial fit for the whole range of residual ~(235)U mass content, albeit with larger statistical uncertainty. Detailed uncertainties quantification was conducted for both the AEFC Singles and Doubles. This includes the analysis of statistical uncertainties, calibration uncertainty, and random uncertainties due to the sensitivity of the AEFC to several sources of uncertainty, namely the FA position, FA orientation, interrogation source position, and ambient pool temperature. An overall total uncertainty of 6 g of ~(235)U is estimated for the Singles and Doubles, which is mainly due to calibration uncertainty (for the Singles) and statistical uncertainty (for the Doubles), and which constitutes 3%-6% of the ~(235)U total mass in the FAs, depending on their level of depletion.
机译:2018年,以色列洛斯阿拉莫斯国家实验室(LANL),内盖夫核研究中心(NRCN)和以色列研究反应堆1(IRR-1)的Soreq核研究中心(SNRC)的参与者进行了一场测量运动,其中使用无损分析仪器高级实验燃料计数器(AEFC)测量了反应堆中14种消耗量不同的用过的燃料组件(FA)。 AEFC专为保障目的而设计,可测量从FA发射的中子(被动中子)和由外部中子源(在此实验中为〜(252)Cf)诱发的裂变中子。 AEFC记录的信号包括总中子计数率(单脉冲),与时间相关的中子计数率(双倍)和总伽马射线计数率。以前通过两种独立的方法评估了FAs的〜(235)U含量:(1)测量FA对活化activated源发出的低能伽马射线的透明性(r伽马透射或RGT方法);以及(2)使用详细的三维蒙特卡洛堆芯耗竭计算来计算堆芯〜30年的燃耗历史。通过RGT方法测量的FA的结果用于构建校准曲线,该校准曲线将AEFC计数率转换为〜(235)U质量。然后,使用未通过RGT方法测量的六个其他FA的AEFC测量来评估校准。从结果可以确定,Doubles校正曲线比Singles校正曲线更可靠,并且对残留〜(235)U质量含量的整个范围遵循简单的二阶多项式拟合,尽管存在较大的统计不确定性。对AEFC单打和双打进行了详细的不确定性量化。这包括由于AEFC对几种不确定性源(即FA位置,FA方向,询问源位置和环境池温度)的敏感性而导致的统计不确定性,校准不确定性和随机不确定性的分析。单打和双打的总总不确定度约为6 g〜(235)U,这主要是由于校准不确定性(针对单打)和统计不确定性(针对双打),占3%-6% FA中〜(235)U总质量的多少,取决于它们的消耗水平。

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