Impact of dopants and leachants on modern UO2-based fuels alteration under final storage conditions: Single and joint effects

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2025-01-17 DOI:10.1016/j.jnucmat.2025.155635
N. Rodríguez-Villagra , S. Fernández-Carretero , A. Milena-Pérez , L.J. Bonales , L. Gutiérrez , J. Cobos , H. Galán
{"title":"Impact of dopants and leachants on modern UO2-based fuels alteration under final storage conditions: Single and joint effects","authors":"N. Rodríguez-Villagra ,&nbsp;S. Fernández-Carretero ,&nbsp;A. Milena-Pérez ,&nbsp;L.J. Bonales ,&nbsp;L. Gutiérrez ,&nbsp;J. Cobos ,&nbsp;H. Galán","doi":"10.1016/j.jnucmat.2025.155635","DOIUrl":null,"url":null,"abstract":"<div><div>Doped-UO<sub>2</sub> fuels such as Cr- or Cr/Al-UO<sub>2</sub> (accident-tolerant fuels (ATF) or modern nuclear fuels) and Gd–UO<sub>2</sub> fuel (being Gd a burnable neutron absorber now in use in LWR fuels) need to be deeply studied not only relating to its advantages under normal and accident conditions in operation, but also its behavior under different repository conditions. After the geologic repository post-closure, once the spent nuclear fuel come into contact with groundwater after container failure, the release of some radionuclides will rely on the UO<sub>2</sub> matrix dissolution processes. The corrosion/dissolution behavior of doped UO<sub>2</sub> fuels, including ATF, in a deep geological repository is barely comprehended. The join influence of dopants and groundwater composition needs further enhance knowledge and understanding by filling gaps in the empirical databases. This study examines the impact of Cr, Cr/Al and Gd dopants on the corrosion of UO<sub>2</sub> fuel pellets in groundwater, based on the known benefits of adding certain soluble metal oxides to UO<sub>2</sub>, depending on the nature of the doping element. Systematic dissolution experiments were conducted with Cr-, Cr/Al-, and Gd-doped UO<sub>2</sub> pellets in three aqueous media with varying pH and HCO<sub>3</sub><sup>−</sup> concentrations. Groundwaters used with increasing the complexity of the system (<em>i.e.</em> contain many ionic species) were 20 mM NaClO<sub>4</sub> (pH 7.2), 19:1 mM NaHCO<sub>3</sub>:NaCl (pH 8.9), and synthetic young cement water with Calcium (pH 13.5). The experiments revealed that the leachant attributes, particularly the combined effects of pH, redox conditions, and HCO<sub>3</sub><sup>−</sup>, had a more significant impact on uranium concentration and dissolution rates than the dopants themselves. No secondary uranium phases were observed on the surfaces of any post-leached samples. These findings contribute to the understanding of the combined effects of doping and aqueous composition on the dissolution behavior of modern nuclear fuels under long-term conditions anticipated in a deep geological repository.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"606 ","pages":"Article 155635"},"PeriodicalIF":3.2000,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525000303","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2025/1/17 0:00:00","PubModel":"Epub","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0

Abstract

Doped-UO2 fuels such as Cr- or Cr/Al-UO2 (accident-tolerant fuels (ATF) or modern nuclear fuels) and Gd–UO2 fuel (being Gd a burnable neutron absorber now in use in LWR fuels) need to be deeply studied not only relating to its advantages under normal and accident conditions in operation, but also its behavior under different repository conditions. After the geologic repository post-closure, once the spent nuclear fuel come into contact with groundwater after container failure, the release of some radionuclides will rely on the UO2 matrix dissolution processes. The corrosion/dissolution behavior of doped UO2 fuels, including ATF, in a deep geological repository is barely comprehended. The join influence of dopants and groundwater composition needs further enhance knowledge and understanding by filling gaps in the empirical databases. This study examines the impact of Cr, Cr/Al and Gd dopants on the corrosion of UO2 fuel pellets in groundwater, based on the known benefits of adding certain soluble metal oxides to UO2, depending on the nature of the doping element. Systematic dissolution experiments were conducted with Cr-, Cr/Al-, and Gd-doped UO2 pellets in three aqueous media with varying pH and HCO3 concentrations. Groundwaters used with increasing the complexity of the system (i.e. contain many ionic species) were 20 mM NaClO4 (pH 7.2), 19:1 mM NaHCO3:NaCl (pH 8.9), and synthetic young cement water with Calcium (pH 13.5). The experiments revealed that the leachant attributes, particularly the combined effects of pH, redox conditions, and HCO3, had a more significant impact on uranium concentration and dissolution rates than the dopants themselves. No secondary uranium phases were observed on the surfaces of any post-leached samples. These findings contribute to the understanding of the combined effects of doping and aqueous composition on the dissolution behavior of modern nuclear fuels under long-term conditions anticipated in a deep geological repository.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
在最终储存条件下,掺杂剂和浸出剂对现代uo2基燃料变化的影响:单一和联合效应
掺杂uo2燃料,如Cr-或Cr/Al-UO2(耐事故燃料(ATF)或现代核燃料)和Gd - uo2燃料(Gd是目前在轻水堆燃料中使用的可燃中子吸收剂),不仅需要深入研究其在正常和事故条件下运行的优势,而且需要深入研究其在不同储存库条件下的行为。地质处置库关闭后,容器失效后乏燃料一旦与地下水接触,部分放射性核素的释放将依赖于UO2基质的溶解过程。掺杂UO2燃料,包括ATF,在深层地质储存库中的腐蚀/溶解行为几乎没有被理解。掺杂剂与地下水组成的联合影响需要通过填补经验数据库的空白进一步增强认识和理解。本研究考察了Cr, Cr/Al和Gd掺杂剂对地下水中UO2燃料颗粒腐蚀的影响,基于在UO2中添加某些可溶性金属氧化物的已知益处,这取决于掺杂元素的性质。研究了Cr-、Cr/Al-和gd掺杂UO2球团在不同pH和HCO3−浓度的三种水介质中的溶解实验。随着系统复杂性的增加(即含有多种离子),使用的地下水为20 mM NaClO4 (pH 7.2), 19:1 mM NaHCO3:NaCl (pH 8.9)和含钙合成水泥水(pH 13.5)。实验结果表明,浸出液性质,特别是pH、氧化还原条件和HCO3−的综合影响,对铀浓度和溶出速率的影响比掺杂剂本身更显著。在浸出后的样品表面未观察到二次铀相。这些发现有助于理解在深地质储存库中长期条件下,掺杂和水组分对现代核燃料溶解行为的综合影响。
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
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
期刊最新文献
Experimental characterization and constitutive modelling of the ratcheting behaviour of EUROFER97/3 steel at high temperatures Positron annihilation spectroscopy investigation of local short range order in neutron-irradiated NiFeMnCr high-entropy alloy Tensile properties and constitutive laws of ITER grade CuCrZr alloy Insights into crevice corrosion in high temperature molten salt system: nickel-based GH3535 alloy exposed to static FLiNaK salt at 700 °C Atomic insights into irradiation induced precipitation in molybdenum-rhenium alloys
×
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
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术
文献互助 智能选刊 最新文献 互助须知 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 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1