Impact of γ irradiation and thermal aging on the swelling pressure of GMZ bentonite

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-06-01 Epub Date: 2025-03-26 DOI:10.1016/j.nucengdes.2025.114012

Wei Liu , Dong Liang , Zhongtian Yang , Chao Gao , Jingli Xie , Meilan Jia

{"title":"Impact of γ irradiation and thermal aging on the swelling pressure of GMZ bentonite","authors":"Wei Liu , Dong Liang , Zhongtian Yang , Chao Gao , Jingli Xie , Meilan Jia","doi":"10.1016/j.nucengdes.2025.114012","DOIUrl":null,"url":null,"abstract":"<div><div>To investigate the combined effects of γ irradiation and thermal aging on the swelling pressure of buffer materials used in the geological disposal of high-level radioactive waste, Gaomiaozi (GMZ) bentonite from Inner Mongolia was herein selected. Samples were irradiated by γ rays and exposed to a combination of γ irradiation followed by thermal aging at 90℃. Swelling pressure tests were then conducted. Results showed that irradiation and thermal aging reduced the swelling pressure of GMZ bentonite. Notably, after irradiating and storing at (25 ± 3)℃ for 360 d, the swelling pressure increased by 51.59 % compared with that of the γ-irradiated sample; the swelling pressure decreased by 75.9 % for the γ irradiation–thermal sequentially aged sample (heated for 180 d). Partial chemical-bond destruction, the transformation of structure trivalent to divalent iron, and the water redistribution in the bentonite were the primary drivers of the decrease in the swelling pressure of GMZ bentonite.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"437 ","pages":"Article 114012"},"PeriodicalIF":2.1000,"publicationDate":"2025-06-01","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/S002954932500189X","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2025/3/26 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

To investigate the combined effects of γ irradiation and thermal aging on the swelling pressure of buffer materials used in the geological disposal of high-level radioactive waste, Gaomiaozi (GMZ) bentonite from Inner Mongolia was herein selected. Samples were irradiated by γ rays and exposed to a combination of γ irradiation followed by thermal aging at 90℃. Swelling pressure tests were then conducted. Results showed that irradiation and thermal aging reduced the swelling pressure of GMZ bentonite. Notably, after irradiating and storing at (25 ± 3)℃ for 360 d, the swelling pressure increased by 51.59 % compared with that of the γ-irradiated sample; the swelling pressure decreased by 75.9 % for the γ irradiation–thermal sequentially aged sample (heated for 180 d). Partial chemical-bond destruction, the transformation of structure trivalent to divalent iron, and the water redistribution in the bentonite were the primary drivers of the decrease in the swelling pressure of GMZ bentonite.

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

γ辐照和热老化对GMZ膨润土膨胀压力的影响

为研究γ辐照和热老化对高放废物地质处置缓冲材料膨胀压力的联合影响，选择了内蒙古高庙子膨润土。样品经γ射线辐照后，在90℃下进行γ辐照后的热时效处理。然后进行膨胀压力试验。结果表明，辐照和热老化降低了GMZ膨润土的膨胀压力。在（25±3）℃下辐照保存360 d后，膨胀压力比γ辐照样品提高了51.59%；γ辐照-热序时效试样（加热180 d）膨胀压力降低75.9%。部分化学键破坏、三价铁结构向二价铁结构转变以及膨润土中水分的重新分布是导致GMZ膨润土膨胀压力降低的主要原因。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文去求助

来源期刊

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.