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

IF 1.9 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

{"title":"Study on permeability from 3D images of nuclear grade graphite IG-110 by the multidimensional capillary bundle model, lattice Boltzmann method and experiment","authors":"Lei Peng , Shen Zhang , Huang Zhang , Jianlin Zhao , Ke Jiang , Wei Zheng , Bin Du , Huaqiang Yin , Xuedong He , Tao Ma","doi":"10.1016/j.anucene.2024.111144","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"213 ","pages":"Article 111144"},"PeriodicalIF":1.9000,"publicationDate":"2024-12-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924008077","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

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.

查看原文本刊更多论文

求助全文

约1分钟内获得全文求助全文

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.