Comparison of the corrosion behavior of four Fe-Cr-Ni austenitic alloys in supercritical water

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

Journal of Nuclear Materials Pub Date : 2024-09-19 DOI:10.1016/j.jnucmat.2024.155409

Tao Huang , Haozhan Su , Yuhao Zhou , Jiamei Wang , Lefu Zhang , Kai Chen

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Abstract

The corrosion behavior of four Fe-Cr-Ni austenitic alloys were investigated after exposure to deaerated supercritical water (SCW) at 650°C. Results show that the corrosion resistance follows the trend:Fe-29Cr-61Ni > Fe-16Cr-75Ni > Fe-25Cr-20Ni > Fe-21Cr-31Ni. The increase in Cr and Ni contents promote a transition from low-protective multilayer oxide scales to protective Cr₂O₃ scales. After surface grinding, the weight gains of all specimens dropped by one order of magnitude. Surface grinding induces the formation of ultrafine grains and a high density of dislocations, which enhances the corrosion resistance among all studied austenitic alloys. However, the beneficial effects of grinding diminish with increased Cr and Ni contents due to the pre-existing portion of Cr₂O₃ scales. The lower critical Cr content required to form Cr₂O₃ scales in high Ni austenitic alloys is primarily attributed to their lower solubility of O and the slower diffusion rates of Ni, which inhibit corrosion behavior.

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四种铁-铬-镍奥氏体合金在超临界水中的腐蚀行为比较

研究了四种铁-铬-镍奥氏体合金在 650°C 下暴露于脱气超临界水 (SCW) 后的腐蚀行为。结果表明，耐腐蚀性的变化趋势为：Fe-29Cr-61Ni；Fe-16Cr-75Ni；Fe-25Cr-20Ni；Fe-21Cr-31Ni。铬和镍含量的增加促进了低保护性多层氧化鳞片向保护性 Cr2O3 鳞片的过渡。表面研磨后，所有试样的增重都下降了一个数量级。表面研磨促使形成超细晶粒和高密度位错，从而提高了所有研究奥氏体合金的耐腐蚀性。然而，随着铬和镍含量的增加，磨削的有益效果会减弱，原因是预先存在部分 Cr2O3 鳞片。在高镍奥氏体合金中，形成 Cr2O3 鳞片所需的临界铬含量较低，这主要是因为它们的 O 溶解度较低，镍的扩散速度较慢，从而抑制了腐蚀行为。

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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.