Study on permeability from 3D images of nuclear grade graphite IG-110 by the multidimensional capillary bundle model, lattice Boltzmann method and experiment

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-12-26 DOI:10.1016/j.anucene.2024.111144

Lei Peng , Shen Zhang , Huang Zhang , Jianlin Zhao , Ke Jiang , Wei Zheng , Bin Du , Huaqiang Yin , Xuedong He , Tao Ma

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Abstract

Nuclear-grade graphite IG110 is extensively utilized in the High Temperature Gas-cooled Reactor’s core. Permeability is a critical parameter to predict its dehumidification performance. However, there are few research about analyzing the permeability of nuclear graphite materials. In this study, through the utilization of high-resolution X-ray microtomographic image (XCT-image), three-dimensional geometries of nuclear graphite IG-110 were generated. Subsequently, a combination of a single relaxation time Lattice Boltzmann Method (SRT-LBM) and a multidimensional capillary bundle model is used for analyzing gas permeabilities based on XCT-image. The results showed that the permeability values computed using the SRT-LBM based on binary images segmented by the otsu thresholding algorithm, are in good agreement with the experimental results. Additionally, the permeability estimated by a multidimensional capillary bundle model somewhat provided a reasonably accurate estimation of the true permeability. Overall, it is expected that this work provide insight on the permeability analysis of similar particulate materials.

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采用多维毛细束模型、晶格玻尔兹曼方法和实验研究核级石墨IG-110三维图像的渗透率

核级石墨IG110广泛应用于高温气冷堆堆芯。透气性是预测其除湿性能的重要参数。然而，关于核石墨材料的磁导率分析的研究很少。本研究利用高分辨率x射线显微层析成像（XCT-image），生成核石墨IG-110的三维几何形状。随后，采用单松弛时间点阵玻尔兹曼方法（SRT-LBM）和多维毛细管束模型相结合的方法，对基于xct图像的气体渗透率进行了分析。结果表明，基于otsu阈值分割算法分割的二值图像，利用SRT-LBM计算的渗透率值与实验结果吻合较好。此外，利用多维毛细管束模型估算的渗透率在一定程度上提供了对真实渗透率较为准确的估计。总的来说，期望这项工作为类似颗粒材料的渗透性分析提供见解。

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来源期刊

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.