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An Analysis Technique for Active Neutron Multiplicity Measurements Based on First Principles

机译:基于第一原理的主动中子多重测量分析技术

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Passive neutron multiplicity counting is commonly used to quantify the total mass of plutonium in a sample, without prior knowledge of the sample geometry. However, passive neutron counting is less applicable to uranium measurements due to the low spontaneous fission rates of uranium. Active neutron multiplicity measurements are therefore used to determine the ~(235)U mass in a sample. Unfortunately, there are still additional challenges to overcome for uranium measurements, such as the coupling of the active source and the uranium sample. Techniques, such as the coupling method, have been developed to help reduce the dependence of calibration curves for active measurements on uranium samples; although, they still require similar geometry known standards. An advanced active neutron multiplicity measurement method is being developed by Texas A&M University, in collaboration with Los Alamos National Laboratory (LANL) in an attempt to overcome the calibration curve requirements. This method can be used to quantify the ~(235)U mass in a sample containing uranium without using calibration curves. Furthermore, this method is based on existing detectors and nondestructive assay (NDA) systems, such as the LANL Epithermal Neutron Multiplicity Counter (ENMC). This method uses an inexpensive boron carbide liner to shield the uranium sample from thermal and epithermal neutrons while allowing fast neutrons to reach the sample. Due to the relatively low and constant fission and absorption energy dependent cross-sections at high neutron energies for uranium isotopes, fast neutrons can penetrate the sample without significant attenuation. Fast neutron interrogation therefore creates a homogeneous fission rate in the sample, allowing for first principle methods to be used to determine the ~(235)U mass in the sample. This paper discusses the measurement method concept and development, including measurements and simulations performed to date, as well as the potential limitations.
机译:被动中子多重计数通常用于量化钚的总质量的样品中,没有样品的几何形状的先验知识。然而,无源中子计数是不太适用于测量铀由于铀的低自发裂变率。因此活性中子多个测量被用来确定〜(235)U质量于样品中。不幸的是,仍然有克服铀测量,如活性源耦合和铀样品额外的挑战。技术,例如作为偶联方法,已经被开发,以帮助减少对铀样品活性测量的校准曲线的依赖;虽然,他们仍然需要相似的几何形状已知标准。一种先进的活性中子多重测定方法是由得克萨斯州A与M大学在试图克服校准曲线的要求开发的,与洛斯阿拉莫斯国家实验室(LANL)协作。该方法可用于定量〜(235)U质量含铀不使用校准曲线于样品中。此外,这种方法是基于现有的检测器和非破坏性试验(NDA)系统,如LANL超热中子多重性计数器(ENMC)。该方法使用廉价的碳化硼衬垫,同时允许快速中子到达样品从热和超热中子屏蔽铀样品。由于在高能量中子为铀同位素的相对低的且恒定的裂变和吸收能量依赖的横截面,快中子能穿透而不会显著衰减样品。因此快速中子探询创建在样品中均匀裂变率,从而允许第一原理方法被用来确定〜(235)U质量于样品中。本文讨论的测定方法的概念和发展,包括迄今进行的测量和模拟,以及潜在的局限性。

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