Corrosion behavior of 304L stainless steel by wire arc additive manufacturing in liquid lead-bismuth eutectic at 550 °C

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-02-01 DOI:10.1016/j.jnucmat.2024.155598

Libo Zhang , Hao Wang , Ke Zhao , Fangqiang Ning , Tianyi Xu , Jia Liu , Hong Yan , Qiang Zhang

引用次数: 0

Abstract

The corrosion behaviors of wire arc additive manufacturing 304L stainless steel (WAAM 304L SS) and forged 304L stainless steel (304L SS) were studied in static oxygen-saturated/depleted lead-bismuth eutectic (LBE) at 550 °C for up to 1000 h. It was found that WAAM 304L SS exhibited better resistance to LBE corrosion than 304L SS under both saturated and depleted oxygen conditions due to its optimized chemical composition and microstructure. Three-layer oxide films were formed on both materials in oxygen-saturated LBE, and δ-ferrite showed stronger oxidation resistance than austenite in WAAM 304L SS. The corrosion mechanism of WAAM 304L SS in oxygen-saturated/depleted liquid LBE are discussed.

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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.