CORTEX 实验,第三部分:以可靠的不确定性对 AKR-2 的零功率传递函数进行实验测定

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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引用次数: 0

摘要

传递函数是核反应堆的一个重要特征量,因为它包含动力学参数。它表示核反应堆对一定频率干扰的响应。如果通过实验确定了它,就可以利用它得出有关动力学参数的结论。本文介绍了德累斯顿工业大学 AKR-2 反应堆零功率传递函数的测量结果以及新的数据分析方法。这些测量结果与通过 MCNP 和 Serpent 进行蒙特卡罗模拟获得的理论零功率传递函数和动力学参数进行了比较。为此,采用了基于引导算法的先进数据分析技术。这些技术抑制了基频倍数以外的信号,并能获得峰值在频域中的完整概率分布。这样就能可靠地估计零功率传递函数测量数据的平均值和不确定性估计值,并量化实验和计算之间的偏差。它还首次确定了 AKR-2 零功率传递函数的相位。在估计的不确定性范围内,实验和计算结果是一致的。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
CORTEX experiments, Part III: Experimental determination of the zero power transfer function of AKR-2 with reliable uncertainties

The transfer function is an important characteristic quantity of a nuclear reactor, since it contains the kinetic parameters. It expresses the response of a nuclear reactor to a disturbance of a certain frequency. If it is determined experimentally, it can be used to draw conclusions about the kinetic parameters. This article presents results of measurements of the zero power transfer function of the AKR-2 reactor at TU Dresden together with new data analysis methods. These measurements are compared to the theoretical zero power transfer function with kinetic parameters obtained via Monte Carlo simulations with MCNP and Serpent. To this end, advanced data analysis techniques based on a bootstrapping algorithms are employed. These techniques suppress the signal outside multiples of the fundamental frequency and additionally allow to obtain the full probability distribution of a peak in the frequency domain. This allowed for a reliable estimation of the mean value and uncertainty estimates of measured data of the zero power transfer function and the quantification of deviations between the experiments and the computations. It also made it possible to determine the phase of the zero power transfer function of AKR-2 for the first time. The experiments and computations are in agreement within the estimated uncertainties.

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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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