T91钢在超临界水环境中的腐蚀性能
Corrosion Behavior of T91 Steel in Supercritical Water
摘 要
在超临界水(SCW)环境中对新型铁素体/马氏体钢T91进行了不同时间的高压釜浸泡试验, 采用SEM、EDS和XRD等方法对试样表面的腐蚀氧化膜进行了分析。结果表明: T91钢在超临界水环境中的氧化符合固态生长机制, 材料表面生成了保护性氧化膜；外层氧化膜的主要成分是Fe3O4, 有大量孔洞和裂纹缺陷；内层氧化膜的主要成分为Fe3O4和FeCr2O4, 结构致密, 随浸泡时间的延长氧化膜分层逐渐清晰；内层氧化膜中FeCr2O4含量逐渐增加, Fe(Fe, Cr)2O4的尖晶石结构具有保护性, 使T91钢在SCW中的腐蚀速率降低。
超临界水
腐蚀性能
martensitic steel T91
supercritical water (SCW)
corrosion behavior
Abstract
The corrosion behavior of ferritic/martensitic steel T91 in supercritical water (SCW) was investigated by immersion test in autoclave for different times, and the oxide films on the surface of samples were characterized using SEM, EDS and XRD techniques. The results show that a dual-layer protective oxide film formed in SCW, consisting of an outer layer with Fe3O4 and an inner layer with Fe3O4 and FeCr2O4. The oxidation fellowed the solid state growth rule. The boundaries between oxide layers became evident with increasing immersion time. The increasing content of FeCr2O4 in inner layer and the protectiveness of Fe(Fe, Cr)2O4 spinel made the corrosion rate decreased.
中图分类号 TG172 DOI 10.11973/fsyfh-201606002
所属栏目 试验研究
基金项目 国家重点基础研究发展规划(973 计划)项目(2007BC209802)
收稿日期 2015/4/30
修改稿日期
网络出版日期
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备注张乐福(1967-), 副教授, 博士, 从事核材料腐蚀研究,
引用该论文: GAO Wen-hua,SHEN Zhao,ZHANG Le-fu. Corrosion Behavior of T91 Steel in Supercritical Water[J]. Corrosion & Protection, 2016, 37(6): 444
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参考文献
【1】USDOE. A technology roadmap for generation Ⅳ nuclear energy systems[J]. Philosophical Review, 2002, 66(2):239-241.
【2】DUFFEY B R, PIORO L I, GABARAEV A B, et al. SCW pressure-channel nuclear reactors:some design features and concepts[C]//International Conference on Nuclear Engineering.[S.l.]:[s.n.], 2006:643-652.
【3】CHOW C K, KHARTABIL H F. Conceptual fuel channel designs for CANDU-SCWR[J]. Nuclear Engineering & Technology, 2008, 40(2):139-146.
【4】周荣灿, 范长信. 超超临界火电机组材料研究及选材分析[J]. 中国电力, 2005, 38(8):41-47.
【5】ATKINSON A. Transport processes during the growth of oxide films at elevated temperature[J]. Review of Modern Physics, 1985, 57(2):437-470.
【6】OLMEDO A M, ALVAREZ M G, DOMNGUEZ G, et al. Corrosion behavior of T91 and type AISI 403 stainless steel in supercritical water[J]. Procedia Materials Science, 2012, 1(16):543-549.
【7】刘秀晨, 安成强. 金属腐蚀学[M]. 北京:国防工业出版社, 2002: 267-273.
【8】STEINER H, KONYS J. Stresses in oxidized claddings and mechanical stability of oxide scales, FZKA-7191[R]. Wissenschaftliche Berichte:[s.n.], 2006.
【9】AMPORNRAT P, WAS G S. Oxidation of ferritic-martensitic alloys T91, HCM12A and HT-9 in supercritical water[J]. Journal of Nuclear Materials, 2007, 371:1-17.
【10】ROBERTSON J. The mechanism of high temperature aqueous corrosion of steel[J]. Corrosion Science, 1989, 29(11/12):1275-1291.
【11】WAS G S, AMPORNRAT P, GUPTA G, et al. Corrosion and stress corrosion cracking in supercritical water[J]. Journal of Nuclear Materials, 2007, 371(1/3):176-201.
【12】GMEZ-BRICEO D, BLZQUEZ F, SEZ-MADERUELO A. Oxidation of austenitic and ferritic/martensitic alloys in supercritical water[J]. Journal of Supercritical Fluids, 2013, 78(5):103-113.
【13】TAN L, REN X, ALLEN T R. Corrosion behavior of 9-12% Cr ferritic-martensitic steels in supercritical water[J]. Corrosion Science, 2010, 52(4):1520-1528.
【14】伯克斯. 金属高温氧化导论[M]. 北京:高等教育出版社, 2010: 41-42.
【15】YI Y, LEE B, KIM S, et al. Corrosion and corrosion fatigue behaviors of 9cr steel in a supercritical water condition[J]. Materials Science & Engineering:A, 2006, 429(1):161-168.
【2】DUFFEY B R, PIORO L I, GABARAEV A B, et al. SCW pressure-channel nuclear reactors:some design features and concepts[C]//International Conference on Nuclear Engineering.[S.l.]:[s.n.], 2006:643-652.
【3】CHOW C K, KHARTABIL H F. Conceptual fuel channel designs for CANDU-SCWR[J]. Nuclear Engineering & Technology, 2008, 40(2):139-146.
【4】周荣灿, 范长信. 超超临界火电机组材料研究及选材分析[J]. 中国电力, 2005, 38(8):41-47.
【5】ATKINSON A. Transport processes during the growth of oxide films at elevated temperature[J]. Review of Modern Physics, 1985, 57(2):437-470.
【6】OLMEDO A M, ALVAREZ M G, DOMNGUEZ G, et al. Corrosion behavior of T91 and type AISI 403 stainless steel in supercritical water[J]. Procedia Materials Science, 2012, 1(16):543-549.
【7】刘秀晨, 安成强. 金属腐蚀学[M]. 北京:国防工业出版社, 2002: 267-273.
【8】STEINER H, KONYS J. Stresses in oxidized claddings and mechanical stability of oxide scales, FZKA-7191[R]. Wissenschaftliche Berichte:[s.n.], 2006.
【9】AMPORNRAT P, WAS G S. Oxidation of ferritic-martensitic alloys T91, HCM12A and HT-9 in supercritical water[J]. Journal of Nuclear Materials, 2007, 371:1-17.
【10】ROBERTSON J. The mechanism of high temperature aqueous corrosion of steel[J]. Corrosion Science, 1989, 29(11/12):1275-1291.
【11】WAS G S, AMPORNRAT P, GUPTA G, et al. Corrosion and stress corrosion cracking in supercritical water[J]. Journal of Nuclear Materials, 2007, 371(1/3):176-201.
【12】GMEZ-BRICEO D, BLZQUEZ F, SEZ-MADERUELO A. Oxidation of austenitic and ferritic/martensitic alloys in supercritical water[J]. Journal of Supercritical Fluids, 2013, 78(5):103-113.
【13】TAN L, REN X, ALLEN T R. Corrosion behavior of 9-12% Cr ferritic-martensitic steels in supercritical water[J]. Corrosion Science, 2010, 52(4):1520-1528.
【14】伯克斯. 金属高温氧化导论[M]. 北京:高等教育出版社, 2010: 41-42.
【15】YI Y, LEE B, KIM S, et al. Corrosion and corrosion fatigue behaviors of 9cr steel in a supercritical water condition[J]. Materials Science & Engineering:A, 2006, 429(1):161-168.
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