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The Verification from Uranium Oxide Powders in Different Forms by Nondestructive Assay Using MCNP5 with Comparison MGAU

机译:使用MCNP5与比较MGAU进行无损分析,从不同形式的氧化铀粉末中验证

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摘要

In this paper, the physical inventory taking of nuclear materials (under safeguards agreement) at a nuclear fuel researchlaboratory has been considered. Nuclear materials with different forms and sizes were verified. The verification method wasbased on nondestructive measurements of gamma radiation emitted from nuclear material. Some of the parameters whichaffect NM mass estimation were calculated using Monte Carlo method. The proposed procedure covers different forms foundat the nuclear fuel research laboratory including spherical, parallelepipeds and cylindrical shapes with different sizes. Thepresent procedure could be very useful for safeguards purposes. Average accuracies for the estimated 235U masses of about− 0.159% and − 0.0935% with a precision of about 2.4% and 7.85% are obtained for MCNP and MGAU, respectively. Thiswork aims to verify experimental measurements of nuclear materials’ samples with different shapes and sizes in a shorttime. These experimental measurements verifications can be quickly performed using the general-purpose Monte CarloN-Particle code (MCNP).
机译:本文考虑了在核燃料研究实验室(根据保障协定)核材料的实物盘存。核材料具有不同的形式和大小。验证方法基于核材料发射的伽马射线的无损测量。利用蒙特卡罗方法计算了影响NM质量估计的一些参数。拟议的程序涵盖了在核燃料研究实验室发现的各种形式,包括球形,平行六面体和具有不同大小的圆柱形状。本程序对于保障目的可能非常有用。对于MCNP和MGAU,估计的235U质量的平均精度分别为-0.159%和-0.0935%,精度分别为2.4%和7.85%。这项工作旨在在短时间内验证对具有不同形状和大小的核材料样品的实验测量。这些实验测量验证可以使用通用的Monte CarloN-Particle代码(MCNP)快速执行。

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