Experimental study on boundary-conditioned hydration impact on bentonite gas permeability with supporting modeling

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Hongyang Ni , Jiangfeng Liu , Qi Zhang , Zhipeng Wang , Zihao Zhang
{"title":"Experimental study on boundary-conditioned hydration impact on bentonite gas permeability with supporting modeling","authors":"Hongyang Ni ,&nbsp;Jiangfeng Liu ,&nbsp;Qi Zhang ,&nbsp;Zhipeng Wang ,&nbsp;Zihao Zhang","doi":"10.1016/j.nucengdes.2025.113940","DOIUrl":null,"url":null,"abstract":"<div><div>Deep geological disposal is currently a widely accepted disposal option for high-level radioactive waste, with bentonite serving as a crucial buffer/backfill material due to its self-sealing properties. Upon groundwater infiltration, the bentonite experiences constrained swelling due to surrounding rock confinement, influencing its hydro-mechanical behavior. While extensive research has explored the relationship between hydration and gas permeability under free-swelling conditions, the impact of constrained swelling remains insufficiently understood. In the present study, these properties under both free and constrained swelling conditions are investigated. The findings reveal that constrained swelling conditions hinder the hydration process, leading to reduced porosity and increased water saturation compared to free-swelling conditions. The temporal variation in water content under both boundary conditions can be described by an adsorption-diffusion equation with a strong correlation (coefficients of determination, R<sup>2</sup> &gt; 0.97, and root mean squared error (RMSE) ≤ 0.0048). Moreover, the van Genuchten (VG) model accurately captures water saturation trends with R<sup>2</sup> = 0.99 and RMSE = 0.012 for free swelling, and R<sup>2</sup> = 0.98 and RMSE = 0.013 for constrained swelling). Despite having comparable water content, constrained swelling significantly reduces gas permeability. Additionally, a higher initial equilibrium relative humidity (<em>RH</em>) corresponds to a larger subsequent gas permeability gap, reaching 2.01 × 10<sup>−16</sup> m<sup>2</sup> at 75 % <em>RH</em> and 5.72 × 10<sup>−16</sup> m<sup>2</sup> at 98 % <em>RH</em>. Void ratio and water saturation, two critical parameters influencing gas permeability, undergo substantial changes during the hydration process. Specifically, changes in the available void ratio due to hydration affect gas permeability. By quantifying post-hydration equilibrium changes in void ratio and saturation, a gas permeability model accounting for different boundary conditions is developed, which demonstrates a relatively effective agreement with experimental data (R<sup>2</sup> = 0.75). This study addresses the knowledge gap on how boundary effects of bentonite hydration influence gas permeability, offering key insights into its long-term performance as a barrier material in nuclear waste repositories.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113940"},"PeriodicalIF":1.9000,"publicationDate":"2025-02-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325001177","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

Deep geological disposal is currently a widely accepted disposal option for high-level radioactive waste, with bentonite serving as a crucial buffer/backfill material due to its self-sealing properties. Upon groundwater infiltration, the bentonite experiences constrained swelling due to surrounding rock confinement, influencing its hydro-mechanical behavior. While extensive research has explored the relationship between hydration and gas permeability under free-swelling conditions, the impact of constrained swelling remains insufficiently understood. In the present study, these properties under both free and constrained swelling conditions are investigated. The findings reveal that constrained swelling conditions hinder the hydration process, leading to reduced porosity and increased water saturation compared to free-swelling conditions. The temporal variation in water content under both boundary conditions can be described by an adsorption-diffusion equation with a strong correlation (coefficients of determination, R2 > 0.97, and root mean squared error (RMSE) ≤ 0.0048). Moreover, the van Genuchten (VG) model accurately captures water saturation trends with R2 = 0.99 and RMSE = 0.012 for free swelling, and R2 = 0.98 and RMSE = 0.013 for constrained swelling). Despite having comparable water content, constrained swelling significantly reduces gas permeability. Additionally, a higher initial equilibrium relative humidity (RH) corresponds to a larger subsequent gas permeability gap, reaching 2.01 × 10−16 m2 at 75 % RH and 5.72 × 10−16 m2 at 98 % RH. Void ratio and water saturation, two critical parameters influencing gas permeability, undergo substantial changes during the hydration process. Specifically, changes in the available void ratio due to hydration affect gas permeability. By quantifying post-hydration equilibrium changes in void ratio and saturation, a gas permeability model accounting for different boundary conditions is developed, which demonstrates a relatively effective agreement with experimental data (R2 = 0.75). This study addresses the knowledge gap on how boundary effects of bentonite hydration influence gas permeability, offering key insights into its long-term performance as a barrier material in nuclear waste repositories.
求助全文
约1分钟内获得全文 求助全文
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.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信