高温水中不同Fe含量Ni-Cr-Fe合金的氧化膜特性
Oxide Film Properties of Ni-Cr-Fe Alloys with Different Iron Content in High Temperature Water Environment
摘 要
通过扫描电子显微镜和透射电子显微镜研究了不同Fe含量Ni-Cr-Fe合金在不同水化学条件的模拟压水堆一回路水环境中的氧化膜特性。结果表明：在310 ℃溶解氢含量2.6 mg/L的模拟压水堆一回路水环境中浸泡978 h，增加合金基体中的Fe含量会增加外层氧化膜中富Fe的尖晶石氧化物，并增加从富Cr的内层氧化膜向基体生长的局部氧化突出；在310 ℃含8 mg/L溶解氧的模拟压水堆一回路水环境中浸泡1 012 h，增加合金基体中的Fe含量会引起外层氧化膜中疏松针状尖晶石氧化物的增加和不规则NiO颗粒的减少，并增加内层氧化膜的厚度和内层氧化膜中疏松区域的面积。
Fe含量
高温水
氧化膜
透射电子显微镜(TEM)
nickel-based alloy
iron content
high temperature water
oxide film
transmission electron microscopy (TEM)
Abstract
Oxide film properties of Ni-Cr-Fe alloys with different iron content in simulated PWR primary water environment with different water chemistry conditions were investigated by scan electron microscopy (SEM) and transmission electron microscopy (TEM). After 978 h of immersion in the high temperature water environment with 2.6 mg/L disolved hydrogen at 310 ℃, the resuts show that increasing the iron content in the alloys promoted the formation of the spinel oxide in the outer oxide layer and the growgh of local oxidation penetrations into the alloy matrix along the interface between the inner layer and alloy matrix. After 1 012 h of immersion in the high temperature water environment with 8 mg/L disolved oxydrogen at 310 ℃, the resuts show that increasing the iron content in the alloy promoted the formation of spinel needle-like oxides and decreased the amount of atactic NiO particles in the outer layer, besides, increased the thickness and porous area in the inner layer.
中图分类号 TG172.82 DOI 10.11973/fsyfh-202011002
所属栏目 试验研究
基金项目 国家自然科学基金（51771107）；上海电气核电设备有限公司与上海大学联合培养博士后项目（T-221715005.014）
收稿日期 2020/5/15
修改稿日期
网络出版日期
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引用该论文: RU Xiangkun,Lü Zhanpeng,YANG Chengdong,TANG Weibao. Oxide Film Properties of Ni-Cr-Fe Alloys with Different Iron Content in High Temperature Water Environment[J]. Corrosion & Protection, 2020, 41(11): 8
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参考文献
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【49】MARCUS P,MAURICE V,STREHBLOW H H. Localized corrosion (pitting):a model of passivity breakdown including the role of the oxide layer nanostructure[J]. Corrosion Science,2008,50(9):2698-2704.
【50】BETOVA I,BOJINOV M,KARASTOYANOV V,et al. Effect of water chemistry on the oxide film on Alloy 690 during simulated hot functional testing of a pressurised water reactor[J]. Corrosion Science,2012,58:20-32.
【2】MACHET A,GALTAYRIES A,ZANNA S,et al. XPS and STM study of the growth and structure of passive films in high temperature water on a nickel-base alloy[J]. Electrochimica Acta,2004,49(22/23):3957-3964.
【3】ZHANG Z M,WANG J Q,HAN E H,et al. Influence of dissolved oxygen on oxide films of alloy 690TT with different surface status in simulated primary water[J]. Corrosion Science,2011,53(11):3623-3635.
【4】ZHANG Z M,WANG J Q,HAN E H,et al. Influence of later-dissolved oxygen on microstructural changes in oxide films formed on alloy 690TT in hydrogenated primary water[J]. Corrosion Science,2015,94:245-254.
【5】KUANG W J,WU X Q,HAN E H. Influence of dissolved oxygen concentration on the oxide film formed on Alloy 690 in high temperature water[J]. Corrosion Science,2013,69:197-204.
【6】WANG J Q,LI X H,HUANG F,et al. Comparison of corrosion resistance of UNS N06690TT and UNS N08800SN in simulated primary water with various concentrations of dissolved oxygen[J]. Corrosion,2014,70(6):598-614.
【7】XU J,SHOJI T. The corrosion behavior of alloy 52 weld metal in cyclic hydrogenated and oxygenated water chemistry in high temperature aqueous environment[J]. Journal of Nuclear Materials,2015,461:10-21.
【8】XU J,SHOJI T. The corrosion behavior of alloy 182 in a cyclic hydrogenated and oxygenated water chemistry in high temperature aqueous environment[J]. Corrosion Science,2016,104:248-259.
【9】SOUSTELLE C,FOUCAULT M,FRAMATOME P C,et al. PWSCC of alloy 600:A parametric study of surface film effects[C]//Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Hoboken:John Wiley & Sons,Inc.,2013:105-113.
【10】QIU Y B,SHOJI T,LU Z P. Effect of Dissolved hydrogen on the electrochemical behaviour of alloy 600 in simulated PWR primary water at 290℃[J]. Corrosion Science,2011,53(5):1983-1989.
【11】KIM T,CHOI K J,YOO S C,et al. Effects of Dissolved hydrogen on the crack-initiation and oxidation behavior of nickel-based alloys in high-temperature water[J]. Corrosion Science,2016,106:260-270.
【12】LU Z P,SHOJI T,XUE H,et al. Deterministic formulation of the effect of stress intensity factor on PWSCC of Ni-base alloys and weld metals[J]. Journal of Pressure Vessel Technology,2013,135(2):21402.
【13】ANDRESEN P L,PETER FORD F. Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems[J]. Materials Science and Engineering:A,1988,103(1):167-184.
【14】FORD F P. Quantitative prediction of environmentally assisted cracking[J]. Corrosion,1996,52(5):375-395.
【15】ARIOKA K,YAMADA T,TERACHI T,et al. Cold work and temperature dependence of stress corrosion crack growth of austenitic stainless steels in hydrogenated and oxygenated high-temperature water[J]. Corrosion,2007,63(12):1114-1123.
【16】LU Z P,SHOJI T,DAN T C,et al. The effect of roll-processing orientation on stress corrosion cracking of warm-rolled 304L stainless steel in oxygenated and deoxygenated high temperature pure water[J]. Corrosion Science,2010,52(8):2547-2555.
【17】LU B T,LUO J L,LU Y C. Correlation between film rupture ductility and PbSCC of alloy 800[J]. Electrochimica Acta,2008,53(12):4122-4136.
【18】TERACHI T,FUJⅡ K,ARIOKA K. Microstructural characterization of SCC crack tip and oxide film for SUS 316 stainless steel in simulated PWR primary water at 320℃[J]. Journal of Nuclear Science and Technology,2005,42(2):225-232.
【19】ANDRESEN P L,MORRA M M. Stress corrosion cracking of stainless steels and nickel alloys in high-temperature water[J]. Corrosion,2008,64(1):15-29.
【20】XU J,XIA S,ZHONG X. The corrosion behavior of nickel-based Alloys 182 and 52 and 316 stainless steel in cyclic hydrogenated and oxygenated water chemistry in high temperature aqueous environment[C]//17th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactor,Ottawa:[s.n.],2015:129-137.
【21】NORRING K,ENGSTRÖM J. Initiation of SCC in nickel base alloys in primary PWR environment:studies at Studsvik since mid 1980s[J]. Energy Materials,2008,3(2):113-118.
【22】MENDONÇA R,BOSCH R W,VAN RENTERGHEM W,et al. Effect of temperature and dissolved hydrogen on oxide films formed on Ni and alloy 182 in simulated PWR water[J]. Journal of Nuclear Materials,2016,477:280-291.
【23】DIECKMANN R,MASON T O,HODGE J D,et al. Defects and cation diffusion in magnetite (Ⅲ.) tracerdiffusion of foreign tracer cations as a function of temperature and oxygen potential[J]. Berichte Der Bunsengesellschaft Für Physikalische Chemie,1978,82(8):778-783.
【24】DIECKMANN R. Point defects and transport properties of binary and ternary oxides[J]. Solid State Ionics,1984,12:1-22.
【25】ROBERTSON J. The mechanism of high temperature aqueous corrosion of stainless steels[J]. Corrosion Science,1991,32(4):443-465.
【26】CHEN J X,LINDBERG F,BELOVA L,et al. High resolution electron microscopy study on oxide films formed on nickel-base alloys X-750,182 and 82 in simulated high flow velocity BWR water conditions[C]//15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. Hoboken:John Wiley & Sons,Inc.,2012:371-383.
【27】DAS N K,SUZUKI K,OGAWA K,et al. Early stage SCC initiation analysis of fcc Fe-Cr-Ni ternary alloy at 288℃:a quantum chemical molecular dynamics approach[J]. Corrosion Science,2009,51(4):908-913.
【28】LIM Y S,KIM S W,HWANG S S,et al. Intergranular oxidation of Ni-based alloy 600 in a simulated PWR primary water environment[J]. Corrosion Science,2016,108:125-133.
【29】SCHREIBER D K,OLSZTA M J,BRUEMMER S M. Grain boundary depletion and migration during selective oxidation of Cr in a Ni-5Cr binary alloy exposed to high-temperature hydrogenated water[J]. Scripta Materialia,2014,89:41-44.
【30】RU X K,LU Z P,CHEN J J,et al. Effects of iron content in Ni-Cr-xFe alloys and immersion time on the oxide films formed in a simulated PWR water environment[J]. Journal of Nuclear Materials,2017,497:37-53.
【31】RU X K,MA J R,LU Z P,et al. Effects of iron content in NiCrFe alloys on the oxide films formed in an oxygenated simulated PWR water environment[J]. Journal of Nuclear Materials,2018,509:29-42.
【32】SENNOUR M,MARCHETTI L,MARTIN F,et al. A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor[J]. Journal of Nuclear Materials,2010,402(2/3):147-156.
【33】MARCHETTI L,MISERQUE F,PERRIN S,et al. XPS study of Ni-base alloys oxide films formed in primary conditions of pressurized water reactor[J]. Surface and Interface Analysis,2015,47(5):632-642.
【34】CARRETTE F,LAFONT M C,LEGRAS L,et al. Analysis and TEM examinations of corrosion scales grown on alloy 690 exposed to PWR environment[J]. Materials at High Temperatures,2003,20(4):581-591.
【35】MARCHETTI L,PERRIN S,RAQUET O,et al. Corrosion mechanisms of Ni-base alloys in pressurized water reactor primary conditions[J]. Materials Science Forum,2008,595/596/597/598:529-537.
【36】FERGUSON J B,LOPEZ H F. Oxidation products of INCONEL alloys 600 and 690 in pressurized water reactor environments and their role in intergranular stress corrosion cracking[J]. Metallurgical and Materials Transactions A,2006,37(8):2471-2479.
【37】MACHET A,GALTAYRIES A,MARCUS P,et al. XPS study of oxides formed on nickel-base alloys in high-temperature and high-pressure water[J]. Surface and Interface Analysis,2002,34(1):197-200.
【38】CHAO C Y,LIN L F,MACDONALD D D. A point defect model for anodic passive films I. Film growth kinetics[J]. J Electrochem Soc,1981,128:1187-1194.
【39】BOJINOV M,FABRICIUS G,KINNUNEN P,et al. Electrochemical study of the passive behaviour of Ni-Cr alloys in a borate solution——a mixed-conduction model approach[J]. Journal of Electroanalytical Chemistry,2001,504(1):29-44.
【40】ZHANG Z M,WANG J Q,HAN E H,et al. Analysis of surface oxide films formed in hydrogenated primary water on alloy 690TT samples with different surface states[J]. Journal of Materials Science & Technology,2014,30(12):1181-1192.
【41】PAYET M,MARCHETTI L,TABARANT M,et al. Corrosion mechanism of a Ni-based alloy in supercritical water:impact of surface plastic deformation[J]. Corrosion Science,2015,100:47-56.
【42】SEO M J,SHIM H S,KIM K M,et al. Influence of surface roughness on the corrosion behavior of Alloy 690TT in PWR primary water[J]. Nuclear Engineering and Design,2014,280:62-68.
【43】HAN G D,LU Z P,RU X K,et al. Improving the oxidation resistance of 316L stainless steel in simulated pressurized water reactor primary water by electropolishing treatment[J]. Journal of Nuclear Materials,2015,467:194-204.
【44】MARCHETTI L,PERRIN S,JAMBON F,et al. Corrosion of nickel-base alloys in primary medium of pressurized water reactors:new insights on the oxide growth mechanisms and kinetic modelling[J]. Corrosion Science,2016,102:24-35.
【45】BEVERSKOG B,PUIGDOMENECH I. Pourbaix diagrams for the ternary system of iron-chromium-nickel[J]. Corrosion,1999,55(11):1077-1087.
【46】BEVERSKOG B,PUIGDOMENECH I. Revised Pourbaix diagrams for nickel at 25-300℃[J]. Corrosion Science,1997,39(5):969-980.
【47】BEVERSKOG B,PUIGDOMENECH I. Revised Pourbaix diagrams for chromium at 25-300℃[J]. Corros Sci,1997,39:43-57.
【48】BEVERSKOG B,PUIGDOMENECH I. Revised pourbaix diagrams for iron at 25-300℃[J]. Corrosion Science,1996,38(12):2121-2135.
【49】MARCUS P,MAURICE V,STREHBLOW H H. Localized corrosion (pitting):a model of passivity breakdown including the role of the oxide layer nanostructure[J]. Corrosion Science,2008,50(9):2698-2704.
【50】BETOVA I,BOJINOV M,KARASTOYANOV V,et al. Effect of water chemistry on the oxide film on Alloy 690 during simulated hot functional testing of a pressurised water reactor[J]. Corrosion Science,2012,58:20-32.
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