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 , Minsoo Lee , Gha-Young Kim , 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.
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