Effect of pre-oxidation on the corrosion behavior of Al-containing ODS steel in oxygen- saturated static LBE at 600 and 700°C

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
{"title":"Effect of pre-oxidation on the corrosion behavior of Al-containing ODS steel in oxygen- saturated static LBE at 600 and 700°C","authors":"","doi":"10.1016/j.jnucmat.2024.155298","DOIUrl":null,"url":null,"abstract":"<div><p>The corrosion behavior of an Al-containing oxide dispersion strengthened (ODS) steel at 600 and 700°C oxygen-saturated static Pb-Bi eutectic was investigated with and without a pre-oxidation heat treatment. Without pre-oxidation, the ODS steel formed a multilayer oxide scale consisting of outer Pb-Fe-O/magnetite and inner Fe-Cr-Al spinel/Cr(Al)-rich film on the surface during the corrosion exposure at 600°C up to 3100 h. In contrast, the pre-oxidized ODS samples was covered by a thin, dense and continuous pre-formed Al<sub>2</sub>O<sub>3</sub> scale, which effectively improved the corrosion resistance. Although the Al<sub>2</sub>O<sub>3</sub> scale was gradually reacted with Pb-O clusters to form Pb-Al-O compound with the prolonged exposure time to 3100 h, the total thickness of oxide layers was still less than about 1 μm. Exposed to elevated temperature of 700 °C, the corrosion mode changed significantly. Both ODS samples spontaneously formed an external Al<sub>2</sub>O<sub>3</sub> during the exposure for 100 h. However, with prolonged exposure time to 500 h at 700 °C, the integrity of the protective Al<sub>2</sub>O<sub>3</sub> scale gradually destructed. Small nodule-like oxides emerged from localized areas in the pre-oxidized samples, while more thicker oxide layer was form in the as-received samples. which intensified corrosion by the aggressive LBE melt. The results suggest that optimized pre-oxidation treatment can effectively to improve the corrosion resistance of Al-containing ODS steel.</p></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":null,"pages":null},"PeriodicalIF":2.8000,"publicationDate":"2024-07-16","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/S0022311524004008","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0

Abstract

The corrosion behavior of an Al-containing oxide dispersion strengthened (ODS) steel at 600 and 700°C oxygen-saturated static Pb-Bi eutectic was investigated with and without a pre-oxidation heat treatment. Without pre-oxidation, the ODS steel formed a multilayer oxide scale consisting of outer Pb-Fe-O/magnetite and inner Fe-Cr-Al spinel/Cr(Al)-rich film on the surface during the corrosion exposure at 600°C up to 3100 h. In contrast, the pre-oxidized ODS samples was covered by a thin, dense and continuous pre-formed Al2O3 scale, which effectively improved the corrosion resistance. Although the Al2O3 scale was gradually reacted with Pb-O clusters to form Pb-Al-O compound with the prolonged exposure time to 3100 h, the total thickness of oxide layers was still less than about 1 μm. Exposed to elevated temperature of 700 °C, the corrosion mode changed significantly. Both ODS samples spontaneously formed an external Al2O3 during the exposure for 100 h. However, with prolonged exposure time to 500 h at 700 °C, the integrity of the protective Al2O3 scale gradually destructed. Small nodule-like oxides emerged from localized areas in the pre-oxidized samples, while more thicker oxide layer was form in the as-received samples. which intensified corrosion by the aggressive LBE melt. The results suggest that optimized pre-oxidation treatment can effectively to improve the corrosion resistance of Al-containing ODS steel.

预氧化对 600 和 700°C 饱和氧气静态 LBE 中含铝 ODS 钢腐蚀行为的影响
研究了含铝氧化物分散强化(ODS)钢在 600 和 700°C 氧饱和静态铅铋共晶条件下经过和未经预氧化热处理的腐蚀行为。未经预氧化处理的 ODS 钢在 600°C 长达 3100 小时的腐蚀暴露过程中,表面形成了由外层 Pb-Fe-O/magnetite 和内层 Fe-Cr-Al 尖晶石/富铬 (Al) 薄膜组成的多层氧化鳞。虽然随着暴露时间延长至 3100 小时,Al2O3 鳞片逐渐与 Pb-O 簇发生反应,形成 Pb-Al-O 化合物,但氧化层的总厚度仍小于约 1 μm。在 700 °C 的高温下,腐蚀模式发生了显著变化。两种 ODS 样品在暴露 100 小时后都自发形成了外部 Al2O3,但随着在 700 °C 下暴露时间延长到 500 小时,保护性 Al2O3 鳞片的完整性逐渐遭到破坏。预氧化样品的局部区域出现了小的结节状氧化物,而接收样品则形成了更厚的氧化层,从而加剧了侵蚀性 LBE 熔体的腐蚀。结果表明,优化的预氧化处理能有效提高含铝 ODS 钢的耐腐蚀性。
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
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.
文献相关原料
公司名称 产品信息 采购帮参考价格
×
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