Exploring the influence of alloying elements (Zr, Si, and V) on the corrosion behavior of FeCoNiCr-based high entropy alloys in supercritical water environment

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.2024.155605

Yuxuan Xia , Shanliang Zhou , Zihang Liang , Xi Huang , Qi Zhao , Huiwang Huang , Haidan Zhao , Yilei Zhan , Changfu Wang , Yujun Xie

引用次数: 0

Abstract

This study investigated the effect of alloying elements Zr, V, and Si on the corrosion behavior of FeCoNiCr-based high entropy alloys in supercritical water. Adding Zr decreased corrosion resistance owing to the formation of a thinner Cr₂O₃ outer layer and a mixed Cr₂O₃ and ZrO₂ inner layer. Adding Si formed a complex oxide film with a triple-layer structure with pores and cracks, accelerating corrosion. By contrast, adding V improved corrosion resistance because the formation of a compacted V_0.87Cr_0.13O_2.7 layer inhibited the diffusion of anions and cations. The corrosion mechanisms were also 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.