304不銹鋼在模擬壓水堆一回路水中高溫電化學腐蝕行為

汪家梅; 陸輝; 張樂福; 孟凡江; 徐雪蓮

doi:10.13374/j.issn2095-9389.2017.03.012

304不銹鋼在模擬壓水堆一回路水中高溫電化學腐蝕行為

doi: 10.13374/j.issn2095-9389.2017.03.012

1) 上海交通大學核能科學與工程學院, 上海 200240
2) 上海核工程研究設計院, 上海 200233

基金項目:

重大專項CAP1400關鍵設計技術研究資助項目（2010ZX06002-001）

詳細信息

中圖分類號: TL341
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出版歷程
- 收稿日期: 2016-05-09

Electrochemical corrosion behavior of 304 stainless steel in simulated pressurized water reactor primary water

1) School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
2) Shanghai Nuclear Engineering Research & Design Institute, Shanghai 200233, China

摘要

摘要: 通過模擬壓水堆一回路水環境，研究了氯離子濃度和溶解氧對304不銹鋼高溫電化學腐蝕行為的影響.動電位極化曲線結果表明，氯離子濃度主要影響高電位下的二次鈍化效應，低電位下影響效果不明顯，結合X射線光電子能譜對氧化膜元素成分的分析發現二次鈍化效應與氧化膜中Fe/Cr元素含量比密切相關.電化學阻抗譜和掃描電鏡結果表明，隨著氯離子濃度增加，氧化膜阻抗逐漸降低，表面外層氧化物顆粒和間隙逐漸增大，耐腐蝕性能降低.隨著溶解氧含量的升高，304自腐蝕電位逐漸升高，鈍化電流密度降低，鈍化區間縮小，表面氧化膜阻抗逐漸增加.
- 不銹鋼 /
- 壓水堆 /
- 高溫 /
- 電化學 /
- 鋼腐蝕
Abstract: The effects of chloride concentration and dissolved oxygen on the high-temperature electrochemical corrosion behaviors of 304 stainless steel sheets were investigated in simulated pressurized water reactor (PWR) primary water. The results of potentiodynamic polarization measurements reveal that the chloride ion mainly affects the second passivation region under high potential, but little effect under low potential. Oxide film chemical content analysis by X-ray photoelectron spectroscopy (XPS) shows that the second passivation properties are closely related to the Fe/Cr ratio of the oxide film. Electrochemical impedance spectroscopy (EIS) and scanning electron microscopy (SEM) results show that, when the chloride ion concentration increases, the oxide film resistance decreases, the size of oxide particles and the gap between oxide particles on the outer layer increases and the corrosion resistance decreases. Besides, with the increase of dissolved oxygen, the corrosion potential increases, the passive current density decreases, the passive potential region shrinks, and the oxide film resistance gradually increases.
- stainless steel /
- pressurized water reactors /
- high temperature /
- electrochemistry /
- steel corrosion

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參考文獻(22)

[1]	Da Cunha Belo M, Walls M, Hakiki N E, et al. Composition, structure and properties of the oxide films formed on the stainless steel 316L in a primary type PWR environment. Corros Sci, 1998, 40(2):447
[2]	Anoop M B, Rao K B, Lakshmanan N. Safety assessment of austenitic steel nuclear power plant pipelines against stress corrosion cracking in the presence of hybrid uncertainties. Int J Pressure Vessels Piping, 2008, 85(4):238
[3]	Li Y K, Lu S P, Li D Z, et al. Remaining life prediction of the core shroud due to stress corrosion cracking failure in BWRs using numerical simulations. J Nucl Sci Technol, 2015, 52(1):96
[4]	Homonnay Z, Kuzmann E, Varga K, et al. Comprehensive investigation of the corrosion state of the heat exchanger tubes of steam generators:Part Ⅱ. Chemical composition and structure of tube surfaces. J Nucl Mat, 2006, 348(1):191
[5]	Bosch R W, Féron D, Celis J P. Electrochemistry in Light Water Reactors:Reference Electrodes, Measurement, Corrosion and Tribocorrosion Issues. Washington:CRC Press, 2007
[6]	Duan Z, Arjmand F, Zhang L, et al. Investigation of the corrosion behavior of 304L and 316L stainless steels at high-temperature borated and lithiated water. J Nucl Sci Technol, 2015, 53(9):1
[7]	Niedrach L W. Use of a high temperature pH sensor as a "Pseudo-Reference Electrode" in the monitoring of corrosion and redox potentials at 285℃. J Electrochem Soc, 1982, 129(7):1445
[8]	Lin C C, Smith F R, Ichikawa N, et al. Electrochemical potential measurements under simulated BWR water chemistry conditions. Corrosion, 1992, 48(1):16
[9]	Kim Y J. Analysis of oxide film formed on type 304 stainless steel in 288 C water containing oxygen, hydrogen, and hydrogen peroxide. Corrosion, 1999, 55(1):81
[10]	Pourbaix M. Altas of electrochemical equilibria in aqueous solutions. Houston:NACE, 1966
[11]	Beverskog B, Puigdomenech I. Pourbaix diagrams for the ternary system of iron-chromium-nickel. Corrosion, 1999, 55(11):1077
[12]	Chen C M, Aral K, Theus G J. Computer-calculated Potential pH Diagrams to 300℃. Volume 2:Handbook of Diagrams. EPRI NP-3137. Alliance:The Babcock & WilcoX Company, 1983
[13]	Tachibana M, Ishida K, Wada Y, et al. Determining factors for anodic polarization curves of typical structural materials of boiling water reactors in high temperature-high purity water. J Nucl Sci Technol, 2012, 49(2):253
[14]	Li X H, Wang J Q, Han E H, et al. Corrosion behavior for Alloy 690 and Alloy 800 tubes in simulated primary water. Corros Sci, 2013, 67:169
[15]	Stellwag B. The mechanism of oxide film formation on austenitic stainless steels in high temperature water. Corros Sci, 1998, 40(2):337
[16]	Ziemniak S E, Hanson M, Sander P C. Electropolishing effects on corrosion behavior of 304 stainless steel in high temperature, hydrogenated water. Corros Sci, 2008, 50(9):2465
[17]	Cristofaro N De, Piantini M, Zacchetti N. The influence of temperature on the passivation behaviour of a super duplex stainless steel in a boric-borate buffer solution. Corros Sci, 1997, 39(12):2181
[18]	Robertson J. The mechanism of high temperature aqueous corrosion of steel. Corros Sci, 1989, 29(11):1275
[19]	Kocijan A, Donik Č, Jenko M. Electrochemical and XPS studies of the passive film formed on stainless steels in borate buffer and chloride solutions. Corros Sci, 2007, 49(5):2083
[20]	Sun H, Wu X Q, Han E H, et al. Effects of pH and dissolved oxygen on electrochemical behavior and oxide films of 304SS in borated and lithiated high temperature water. Corros Sci, 2012, 59:334
[21]	Huang J B, Wu X Q, Han E H. Electrochemical properties and growth mechanism of passive films on Alloy 690 in high-temperature alkaline environments. Corros Sci, 2010, 52(10):3444
[22]	Feng Z C, Cheng X Q, Dong C F, et al. Effects of dissolved oxygen on electrochemical and semiconductor properties of 316L stainless steel. J Nucl Mater, 2010, 407(3):171