Corrosion Resistance of 9Cr Oxide Dispersion Strengthened Steel in Supercritical Water
摘 要
研究了氧化物弥散强化钢9Cr-ODS(K3)在500 ℃/25 MPa条件下的腐蚀行为,对比分析了K3、两种非ODS钢K1(12Cr)和K2(9Cr)在超临界水(SCW)中的抗腐蚀性能。通过扫描电镜-电子能谱(SEM-EDX)、X射线衍射(XRD)、腐蚀增重等分析了氧化膜的显微形貌、结构、相组成及腐蚀动力学规律。结果表明,K1和K2钢在超临界水中腐蚀后,氧化膜中存在许多小孔,而K3钢中小孔数量很少。K3钢在超临界水中生成的氧化膜分为三层结构,分别为外层氧化膜、内层氧化膜和内氧化区。外层氧化膜为Fe3O4,内层氧化膜为FeCr2O4和Fe3O4相,内氧化区是合金元素和氧由氧化膜向基体逐渐过渡的区域。在超临界水中,K1、K2和K3钢的腐蚀动力学均遵循抛物线规律,K3抗腐蚀性能优于9Cr的K2钢,甚至优于12Cr的K1。
Abstract
The oxidation behavior of a 9Cr oxide dispersion strengthened (ODS) steel exposed to supercritical water at 500 ℃ and 25 MPa was examined. For comparison, two non-ODS steels K1 (12Cr) and K2 (9Cr) were also examined. The oxidized samples were characterized using gravimetry, scanning electron microscopy/energy dispersive X-ray spectroscopy and X-ray diffraction. The oxide scales were rather porous in two non-ODS steels K1 and K2, while the porosity in 9Cr-ODS almost couldn′t be observed. A three-layered oxide scale formed on 9Cr-ODS steel, which was mainly composed of an outer oxide layer (Fe3O4), an inner oxide layer (Fe3O4 + FeCr2O4) and an internal oxide zone which was featured by gradual variation of alloying elements and oxygen from the oxide to the matrix. The kinetic data of 9Cr-ODS, two non-ODS steels showed that oxide scale formation obeyed a parabolic rate law. The oxidation rate of 9Cr-ODS steel was lower than that of K2 (9Cr), even more it was lower than that of K1 (12Cr).
中图分类号 TG171
所属栏目 试验研究
基金项目 核能开发项目(超临界水冷堆技术研发); 国家重点基础研究发展规划(973计划)项目(2007CB209800); 四川省青年科技基金(2010JQ0025)
收稿日期 2013/5/7
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备注张强(1982-),助理研究员,硕士,从事反应堆材料性能的评价工作,
引用该论文: YIN Kai-ju,ZHANG Qiang,QIU Shao-yu,TANG Rui. Corrosion Resistance of 9Cr Oxide Dispersion Strengthened Steel in Supercritical Water[J]. Corrosion & Protection, 2014, 35(6): 568
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参考文献
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【4】CHEN Y,SRIDHARAN K,UKAI S H,et al. Oxidation of 9Cr oxide dispersion strengthened steel exposed in supercritical water[J]. Journal of Nuclear Materials,2007,371:118-128.
【5】CHEN Y,SRIDHARAN K,TODD R A,et al. Microstructural examination of oxide layers formed on an oxide dispersion strengthened ferritic steel exposed to supercritical water[J]. Journal of Nuclear Materials,2006,359:50-58.
【6】CHO H S. Corrosion Properties of Oxide Dispersion Strengthened Steels in Supercritical Water Environment[J]. Journal of Nuclear Materials,2004(329-333):387-391.
【7】CASTRO V DE,LEGUEY T,MUNZ A,et al. Microstructural characterization of Y2O3 ODS-Fe-Cr model alloys[J]. Journal of Nuclear Materials,2009(386-388):449-452.
【8】YIN K J,QIU S Y,TANG R,et al. Corrosion behavior of ferritic/martensitic steel P92 in supercritical water[J]. Supercritical Fluids,2009,50:235-239.
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