An iterative scheme to include turbulent diffusion in advective-dominated transport of delayed neutron precursors

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-14 DOI:10.1016/j.anucene.2025.111251
Mathis Caprais , André Bergeron
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Abstract

In this study, the Method of Characteristics (MOC) for Delayed Neutron Precursors (DNPs) is used to solve the precursors balance equation with turbulent diffusion. The diffusivity of DNPs, significantly higher than molecular diffusivity, emerges in turbulent flows from the time-averaging of the DNPs mass balance equation. To integrate this effect within the MOC framework, the advection–reaction component of the DNPs balance equation is solved using the MOC, while the diffusive source is computed from the concentration of the previous iteration. The method is validated on a 2D recirculating pipe reactor with high Reynolds number flow, comparing the MOC with diffusion to a standard finite volume (FV) discretization of the fission products balance equation. Additionally, the impact of the diffusivity term on DNP distributions and reactor reactivity is quantified as a function of the turbulent Schmidt number.
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将湍流扩散纳入以平流为主的延迟中子前体输运的迭代方案
本文采用延迟中子前驱体的特性法(MOC)来求解具有湍流扩散的前驱体平衡方程。从DNPs质量平衡方程的时间平均来看,湍流中DNPs的扩散系数明显高于分子扩散系数。为了在MOC框架内整合这种效应,我们使用MOC求解DNPs平衡方程的平流-反应分量,而扩散源则由前一次迭代的浓度计算。在一个高雷诺数流动的二维循环管式反应器上验证了该方法,并将扩散的MOC与裂变产物平衡方程的标准有限体积离散化进行了比较。此外,扩散系数项对DNP分布和反应堆反应性的影响被量化为湍流施密特数的函数。
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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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