冷加工对铅铋共晶（LBE）中铝形成奥氏体（AFA）钢在600℃下10-6 wt.%氧气氧化行为的高分辨率表征

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-03-01 Epub 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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摘要

采用高分辨率表征技术研究了溶液退火和冷加工表面磨削的AFA钢在600°C和10-6 wt.%氧气条件下暴露于LBE。暴露500小时后，两种钢都形成了保护性氧化层。1700 h后，固溶退火钢出现溶解腐蚀坑，这是由于表面磨削亚表面再结晶形成的细小晶粒中的Cr和Al被耗尽，形成内部（Cr, Al）2O3结核，导致最初形成的氧化鳞片因局部应力增加而脱落。冷加工后，位错和晶界的增加促进了Cr&；Al在地下的补充，保持了外部（Cr, Al）2O3层的耐久性，防止了溶解攻击。

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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

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.