High-resolution characterization of cold working effects on the oxidation behavior of alumina-forming austenitic (AFA) steel in lead-bismuth eutectic (LBE) with 10–6 wt.% oxygen at 600 °C

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-07 DOI:10.1016/j.jnucmat.2025.155691

Decang Zhang , Xiaoxin Zhang , Xian Zeng , Jun Zhang , Hao Ren , Fanao Meng , Qingzhi Yan

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Abstract

The solution-annealed and cold-worked AFA steels with surface grinding exposed to LBE at 600 °C with 10^–6 wt.% oxygen were investigated using high-resolution characterization techniques. After 500 h exposure, both steels developed protective oxide scales. After 1700 h, solution-annealed steel exhibited dissolution corrosion pits, because Cr and Al in fine grains formed by recrystallization of the surface-grinding subsurface were depleted, forming internal (Cr, Al)₂O₃ nodules that caused the initially developed oxide scales to exfoliate due to increased local stress. Following cold working, increased dislocations and grain boundaries facilitated replenishment of Cr&Al in the subsurface, maintaining the durability of external (Cr, Al)₂O₃ scales, preventing dissolution attack.

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来源期刊

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.