The two point Feynman-α theory: Theory and practice of Ex-Core reactor noise measurement

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-04-01 Epub Date: 2024-12-26 DOI:10.1016/j.anucene.2024.111140
C. Dubi , E. Magali , O. Ozeri , A. Krakovich , A. Pesach , O. Rivin , I. Levy
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Abstract

The Feynman-α method is a widely used realization of the so-called ”reactor noise” theory, where static and kinetic parameters of the core are estimated by sampling statistical properties of the neutron count distribution in a critical or subcritical configuration. In the Feynman-α method, the variance-to-mean ratio (as a function of the detection gate) is sampled, and then the α eigenvalue is estimated through a standard fitting procedure. The theory behind the Feynman-α method relies on a single-group analysis. From a practical point of view, the single group model requires that the detector be located within or next to the reactor core.
Implementation of the Feynman-α method is simple and robust due to three facts: first, although the dynamics are determined by (at least) 5 parameters, the fit is done only for a two-parameter function. Second, these parameters are well separated: one is a constant multiplier and the second is an exponential coefficient. Third, the exponential coefficient has a clear and simple physical interpretation, which can be easily used to estimate the reactivity of the core. In the past decade, the classic Feynman-α theory has been extended to a multi-group setting, using the probability generating function formalism. However, in the resulting formulas, it seems, the above mentioned properties are often lost: implementation would require a fit on a multi-exponential function, whose decay modes are defined by the eigenvalues of a certain ”reaction rate” matrix, which may not be explicitly computed, and would depend on parameters that cannot be calibrated in a simple manner.
The present study introduces a simple two-group model, for two distinct spatial regions: the core region and the moderator/reflector region. It assumes that the detector is located outside the core, within the moderator/reflector region. Through direct analysis of the reaction rate matrix, we address the practical applications of the two-point Feynman-α theory: when should we expect a good ”separation” between the different decay modes, and when would the reactivity be tractable from standard fitting procedure. This study starts with the theoretical derivation, then we first conduct a numeric study to verify the conditions for applying the two region model, and second we use the two region model to revisit Ex-Core noise experiments conducted the IPEM/MB-01 and the CROCUS reactors.
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两点费曼α理论:前堆噪声测量的理论与实践
费曼-α方法是一种广泛使用的所谓“反应堆噪声”理论的实现,其中堆芯的静态和动力学参数是通过在临界或亚临界配置中中子计数分布的抽样统计特性来估计的。在Feynman-α方法中,对方差均值比(作为检测门的函数)进行采样,然后通过标准拟合程序估计α特征值。费曼-α方法背后的理论依赖于单群分析。从实用的角度来看,单组模型要求探测器位于反应堆堆芯内部或旁边。由于三个事实,Feynman-α方法的实现简单而稳健:首先,尽管动力学由(至少)5个参数决定,但只对两个参数函数进行拟合。其次,这些参数分离得很好:一个是常数乘数,另一个是指数系数。第三,指数系数具有清晰简单的物理解释,可以很容易地用来估计堆芯的反应性。在过去的十年中,经典的费曼-α理论已经扩展到多群设置,使用概率生成函数的形式。然而,在得到的公式中,上述性质似乎经常丢失:实现将需要对多指数函数进行拟合,其衰减模式由某个“反应速率”矩阵的特征值定义,该矩阵可能无法显式计算,并且依赖于无法以简单方式校准的参数。本研究引入了一个简单的两组模型,用于两个不同的空间区域:核心区和调节/反射区。它假设探测器位于堆芯外,在慢化剂/反射器区域内。通过对反应速率矩阵的直接分析,我们解决了两点费曼-α理论的实际应用:什么时候我们应该期望不同衰变模式之间有良好的“分离”,什么时候反应性可以从标准拟合程序中处理。本研究从理论推导入手,通过数值研究验证了两区模型的适用条件,并利用两区模型重新考察了IPEM/MB-01和CROCUS反应堆的前堆噪声实验。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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