首页> 外文期刊>Nuclear Instruments & Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment >Analysis of experimental measurements of PWR fresh and spent fuel assemblies using Self-Interrogation Neutron Resonance Densitometry
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Analysis of experimental measurements of PWR fresh and spent fuel assemblies using Self-Interrogation Neutron Resonance Densitometry

机译:自审中子共振光密度法分析压水堆新鲜和乏燃料组件的实验测量结果

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摘要

Self-Interrogation Neutron Resonance Densitometry (SINRD) is a new NDA technique that was developed at Los Alamos National Laboratory (LANL) to improve existing nuclear safeguards measurements for LWR fuel assemblies. The SINRD detector consists of four fission chambers (FCs) wrapped with different absorber filters to isolate different parts of the neutron energy spectrum and one ion chamber (IC) to measure the gross gamma rate. As a result, two different techniques can be utilized using the same SINRD detector unit and hardware. These techniques are the Passive Neutron Multiplication Counter (PNMC) method and the SINRD method. The focus of the work described in this paper is the analysis of experimental measurements of fresh and spent PWR fuel assemblies that were performed at LANL and the Korea Atomic Energy Research Institute (KAERI), respectively, using the SINRD detector. The purpose of these experiments was to assess the following capabilities of the SINRD detector: 1) reproducibility of measurements to quantify systematic errors, 2) sensitivity to water gap between detector and fuel assembly, 3) sensitivity and penetrability to the removal of fuel rods from the assembly, and 4) use of PNMC/SINRD ratios to quantify neutron multiplication and/or fissile content. The results from these simulations and measurements provide valuable experimental data that directly supports safeguards research and development (R&D) efforts on the viability of passive neutron NDA techniques and detector designs for partial defect verification of spent fuel assemblies.
机译:自审中子共振光密度法(SINRD)是洛斯阿拉莫斯国家实验室(LANL)研发的一种新的NDA技术,用于改善轻水堆燃料组件的现有核保障措施。 SINRD检测器由四个裂变室(FC)包裹,这些裂变室包裹有不同的吸收剂过滤器以隔离中子能谱的不同部分,而一个离子室(IC)则用于测量总伽马率。结果,可以使用相同的SINRD检测器单元和硬件来利用两种不同的技术。这些技术是无源中子乘法计数器(PNMC)方法和SINRD方法。本文介绍的工作重点是分别使用SINRD检测器对分别在LANL和韩国原子能研究院(KAERI)进行的新鲜和废PWR燃料组件的实验测量进行分析。这些实验的目的是评估SINRD检测器的以下功能:1)测量的可重复性以量化系统误差; 2)对检测器与燃料组件之间的水隙的敏感性; 3)对从中移除燃料棒的敏感性和渗透性。 4)使用PNMC / SINRD比来量化中子倍增和/或裂变含量。这些模拟和测量的结果提供了宝贵的实验数据,这些数据直接支持针对无源中子NDA技术和用于乏燃料组件的部分缺陷验证的检测器设计可行性的保障研究与开发(R&D)努力。

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