利用基于晶格玻尔兹曼法的模型,对流经棒束和/或碎片床几何形状的铈流进行数值模拟

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-09-24 DOI:10.1016/j.nucengdes.2024.113603
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引用次数: 0

摘要

我们提出了一个新模型,用于研究轻水反应堆(LWR)严重事故中不同配置(棒束、多孔碎片床)中热冕流的迁移和分布。我们的模型依赖于解决非饱和铈流体力学问题的改进型晶格玻尔兹曼法(LBM)(称为自由表面 LBM)和解决热传递问题的有限体积法(FVM)之间的耦合。通过实施温度与粘度之间的相关性,解决了铈凝固和熔化问题。对具有代表性的基本体积进行了多次模拟,并改变了配置(碎屑床、带网格和不带网格的棒束)。从结果来看,可以捕捉到低于孔隙尺度的流动的重要细节,同时也可以考虑到多个孔隙尺度的平均效应。作为概念验证,这些初步研究表明,这种 CFD 方法可以确定微观结构尺度上的哪些参数有可能在宏观尺度上控制铈的迁移动力学。它将提供有用的信息,从而改进严重事故代码(如 ASTEC)中的堆芯降解模型。
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Numerical simulation of corium flow through rod bundle and/or debris bed geometries with a model based on Lattice Boltzmann method
A new model is proposed to investigate the relocation and the distribution of hot corium flows in different configurations (rod bundle, porous debris bed) representative of a severe accident in a Light Water Reactor (LWR). Our model relies on the coupling between a modified Lattice Boltzmann Method (LBM), called Free-Surface LBM, that solves hydrodynamics of unsaturated corium and a Finite Volume Method (FVM) that solves heat transfers. Corium solidification and melting are addressed by implementing a correlation between the temperature and the viscosity. Several simulations on representative elementary volumes were performed, varying configurations (debris bed, rod bundle with and without grid). From the results, it is possible to capture important details of the flow at a scale lower than the pore scale and, at the same time, it is possible to take into account the average effects at the scale of several pores. Presented as a proof of concept these preliminary studies show the interest of this kind of CFD approach to identify which parameters at microstructure scale can potentially govern the corium relocation kinetics at macroscopic scale. It will provide useful information that might improve core degradation models in severe accident codes, such as ASTEC.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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