Long-term performance test of Cu canisters used for disposing of spent nuclear fuels under aerobic groundwater

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Junhyuk Jang , Minsoo Lee , Gha-Young Kim , Seok Yoon
{"title":"Long-term performance test of Cu canisters used for disposing of spent nuclear fuels under aerobic groundwater","authors":"Junhyuk Jang ,&nbsp;Minsoo Lee ,&nbsp;Gha-Young Kim ,&nbsp;Seok Yoon","doi":"10.1016/j.net.2025.103678","DOIUrl":null,"url":null,"abstract":"<div><div>Evaluating the long-term corrosion behavior of Cu under local groundwater is important for its use in fabricating disposal canisters. The long-term performance of KJ-I bentonite-embedded Cu disks was assessed for a testing period of 10 years. The results were compared with those obtained on MX-80 bentonite-embedded Cu disks. The disks retrieved from the MX-80 and KJ-I bentonites exhibited corrosion depths of 0.53 and 3.9 μm, respectively. The corrosion rate below 0.39 μm/year indicated that Ca-type KJ-I bentonite can also be used as a buffer material. The surface characterizations revealed the formation of a thin Cu oxide layer (∼0.5 μm) on the MX-80 bentonite-retrieved disk. A Cu<sub>2</sub>O layer (∼2 μm) was formed on the KJ-I bentonite-retrieved disk. During open-circuit potential measurements, the bentonite-embedded disk exhibited a potential below −125 mV, which is considerably lower than the pitting potential of Cu (∼250 mV), indicating that the occurrence of localized corrosion of Cu is largely reduced upon embedding in bentonite. This study demonstrates that KJ-I bentonite-embedded Cu canisters can be utilized for nuclear waste disposal under aerobic conditions.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 9","pages":"Article 103678"},"PeriodicalIF":2.6000,"publicationDate":"2025-04-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Technology","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S1738573325002463","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

Evaluating the long-term corrosion behavior of Cu under local groundwater is important for its use in fabricating disposal canisters. The long-term performance of KJ-I bentonite-embedded Cu disks was assessed for a testing period of 10 years. The results were compared with those obtained on MX-80 bentonite-embedded Cu disks. The disks retrieved from the MX-80 and KJ-I bentonites exhibited corrosion depths of 0.53 and 3.9 μm, respectively. The corrosion rate below 0.39 μm/year indicated that Ca-type KJ-I bentonite can also be used as a buffer material. The surface characterizations revealed the formation of a thin Cu oxide layer (∼0.5 μm) on the MX-80 bentonite-retrieved disk. A Cu2O layer (∼2 μm) was formed on the KJ-I bentonite-retrieved disk. During open-circuit potential measurements, the bentonite-embedded disk exhibited a potential below −125 mV, which is considerably lower than the pitting potential of Cu (∼250 mV), indicating that the occurrence of localized corrosion of Cu is largely reduced upon embedding in bentonite. This study demonstrates that KJ-I bentonite-embedded Cu canisters can be utilized for nuclear waste disposal under aerobic conditions.
在好氧地下水下处理乏核燃料用铜罐的长期性能试验
评价铜在当地地下水中的长期腐蚀行为对铜在处理罐中的应用具有重要意义。通过为期10年的试验,对kj - 1膨润土嵌入铜片的长期性能进行了评估。比较了MX-80膨润土包埋铜片的实验结果。从MX-80和kj - 1膨润土中提取的圆盘腐蚀深度分别为0.53和3.9 μm。腐蚀速率低于0.39 μm/年,表明ca型KJ-I型膨润土也可以作为缓冲材料。表面表征表明,在MX-80膨润土回收盘上形成了一层薄薄的氧化铜层(~ 0.5 μm)。在kj - 1膨润土回收盘上形成Cu2O层(~ 2 μm)。在开路电位测量中,膨润土包埋圆盘的电位低于- 125 mV,远低于Cu的点蚀电位(~ 250 mV),这表明在膨润土包埋后,Cu的局部腐蚀发生大大减少。本研究表明,kj - 1膨润土包埋铜罐可用于好氧条件下的核废料处理。
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 求助全文
来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
×
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:604180095
Book学术官方微信