{"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.
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.