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Computational study of Passive Neutron Albedo Reactivity (PNAR) measurement with fission chambers

机译:裂变室测量被动中子反照率(pNaR)的计算研究

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摘要

The Passive Neutron Albedo Reactivity technique (PNAR) was used to assay used nuclear fuel as a potential method for the measurement of fissionable material in fuel assemblies. A Monte Carlo transport code (MCNPX 2.6) was used to develop simulation models to evaluate the PNAR technique. The MCNPX simulated models consisted of two 17x17 Pressurized Water Reactor (PWR) used fuel assemblies; one with an initial 3 wt% uranium-235*, cooled for 20 years and second with an initial 4 wt% uranium-235*, cooled for 5 years. Each used fuel assembly was simulated at four different burn up rates of 15, 30, 45, and 60 GWd/tU. Four fission chamber (FC) detectors were placed around the used fuel assembly. The four FC detectors considered in this study used Highly Enriched Uranium (HEU), Uranium Dioxide (UO 2 ), Depleted Uranium (DU) and Thorium (Th) FC detectors as the neutron detection material.The purpose of this study as to understand the characteristics of PNAR method and to identify a FC detector system to analyze used nuclear fuel assemblies. Results showed HEU FC detectors responded better than the other FC detectors based on cadmium ratio and on the precision counting time. The cadmium ratio response using the PNAR measurement technique with both PWR Fuel Assemblies 1 and 2, the HEU FC detector performed 0.3% better than UO 2 , 3% better than DU and 30% better than thorium FC detectors. Based upon the detector counting time for both PWR fuel assemblies 1 and 2, the HEU FC detectoru27s counting time was less than one minute, considerably less than the other three FC detectors.
机译:被动中子反照率反应技术(PNAR)用于分析用过的核燃料,作为测量燃料组件中可裂变材料的潜在方法。使用蒙特卡洛运输代码(MCNPX 2.6)开发仿真模型以评估PNAR技术。 MCNPX模拟模型由两个17x17压水堆(PWR)二手燃料组件组成。一种是最初的3 wt%铀235 *冷却了20年,第二种是最初的4 wt%铀235 *冷却了5年。每个用过的燃料组件都以15、30、45和60 GWd / tU的四种不同燃尽率进行了模拟。将四个裂变室(FC)检测器放置在用过的燃料组件周围。本研究中考虑的四个FC探测器使用高浓铀(HEU),二氧化铀(UO 2),贫铀(DU)和Thor(Th)FC探测器作为中子探测材料。 PNAR方法的特点,并确定用于分析二手核燃料组件的FC检测器系统。结果表明,基于镉比和精确计数时间,HEU FC检测器的响应优于其他FC检测器。使用PWR燃料组件1和2的PNAR测量技术得到的镉比率响应,HEU FC检测器的性能比UO 2高0.3%,比DU高3%,比th FC高30%。根据两个PWR燃料组件1和2的检测器计数时间,HEU FC检测器的计数时间少于一分钟,比其他三个FC检测器要少得多。

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    De La Cruz Sandra;

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  • 年度 2011
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  • 原文格式 PDF
  • 正文语种 English
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