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 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2025-01-03 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
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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 V0.87Cr0.13O2.7 layer inhibited the diffusion of anions and cations. The corrosion mechanisms were also discussed.
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探讨了合金元素(Zr、Si、V)对feconicr基高熵合金在超临界水环境中的腐蚀行为的影响
研究了合金元素Zr、V和Si对feconicr基高熵合金在超临界水中腐蚀行为的影响。Zr的加入降低了材料的耐蚀性,形成了较薄的Cr2O3外层和混合的Cr2O3和ZrO2内层。硅的加入使氧化膜形成具有孔隙和裂纹的复杂三层结构,加速了腐蚀。相比之下,V的加入提高了材料的耐蚀性,因为形成致密的V0.87Cr0.13O2.7层抑制了阴离子和阳离子的扩散。并对腐蚀机理进行了讨论。
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来源期刊
Journal of Nuclear Materials
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.
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