Effects of reduced sulfur on the corrosion behavior of Alloy 600 in high-temperature water

被引:11
作者
Lee, E. H. [1 ]
Kim, K. M. [1 ]
Kim, U. C. [1 ]
机构
[1] Korea Atom Energy Res Inst, Dept Nucl Mat Technol Dev, Taejon 305600, South Korea
来源
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING | 2007年 / 449卷
关键词
stress corrosion cracking; steam generator; Alloy; 600; sulfate; reduced sulfur;
D O I
10.1016/j.msea.2006.02.424
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
The effects of reduced sulfur on the corrosion behavior of Alloy 600 MA were investigated in deaerated 0.01 M of sodiumsulfate (Na2SO4), sodium tetrathionate (Na2S4O6), and sodium thiosulfate (NaS2O3) solutions using potentiodynamic polarization and stress corrosion cracking (SCC) tests at 300 degrees C and 340 degrees C. The polarization curves of Alloy 600 MA showed a stable passivity in the Na2SO4 solution; however, the solutions of Na2S4O6 and Na2S2O3 showed accelerated anodic dissolution. The SCC susceptibility of Alloy 600 MA increased in the following order: in the Na2S2O3, Na2SO4, and Na2S4O6 solutions. Results of deposits and spectra taken from an energy dispersive X-ray system confirmed the existence of reduced sulfur. (c) 2006 Elsevier B.V. All rights reserved.
引用
收藏
页码:330 / 333
页数:4
相关论文
共 11 条
[1]  
AGRAWAL AK, 1986, NP4504LD EPRI
[2]  
Bouvier O., 1999, P 9 INT S ENV DEGR M, P695
[3]  
Bouvier O., 2002, P 10 INT S ENV DEGR
[4]  
COMBRADE P, 1989, P 4 INT S ENV DEGR M, P75
[5]  
Daret J., 2002, P 9 INT S ENV DEGR M, P567
[6]   Effects of the valence of sulfur on passivation of alloys 600, 690, and 800 at 25°C and 95°C [J].
Fang, Z ;
Staehle, RW .
CORROSION, 1999, 55 (04) :355-379
[7]  
Lee EH, 2004, MET MATER-INT, V10, P269
[8]  
LUMSDEN JB, 1989, P 4 INT S ENV DEGR M, P6
[9]   THE ANTAGONISTIC ROLES OF CHROMIUM AND SULFUR IN THE PASSIVATION OF NI-CR-FE ALLOYS STUDIED BY XPS AND RADIOCHEMICAL TECHNIQUES [J].
MARCUS, P ;
GRIMAL, JM .
CORROSION SCIENCE, 1990, 31 :377-382
[10]  
Ogawa N, 1997, PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, P395