Effects of sulfur oxyanions and magnetite on the corrosion behavior of alloy 600 under simulated PWR secondary water conditions

被引：0

作者：

Han, Jeoh ^{[1
,2
]}

Hur, Do Haeng ^{[1
]}

Song, Geun Dong ^{[3
]}

Jeon, Soon-Hyeok ^{[1
]}

机构：

[1] Korea Atom Energy Res Inst, Mat Safety Technol Res Div, Daejeon, South Korea

[2] Korea Hydro & Nucl Power Co Ltd, Cent Res Inst, Daejeon, South Korea

[3] FNC Technol Co Ltd, Nucl Mat Res Grp, Gyeonggi Do, South Korea

来源：

JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T | 2024年 / 33卷

基金：

新加坡国家研究基金会;

关键词：

Alloy; 600; Sulfur oxyanions; Magnetite; Corrosion; Oxide film; Potentiodynamic polarization; GENERATOR TUBING ALLOYS; GALVANIC CORROSION; QUANTITATIVE ASSESSMENT; CHLORIDE-IONS; CRACKING; STRESS; LEAD; TEMPERATURE; THIOSULFATE; SULFATE;

D O I：

10.1016/j.jmrt.2024.11.270

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

This study investigates the corrosion behavior of Alloy 600 in sulfur oxyanions (sulfate and tetrathionate) solutions. The corrosion rate and oxide thickness of Alloy 600 drastically increase by the presence of sulfur oxyanions in the environment. The phenomenon is mainly caused by tetrathionate ions, not sulfate ions. When Alloy 600 and magnetite are electrically connected in the solutions, they respectively behave as an anode and a cathode. This galvanic coupling effect further accelerates the corrosion of Alloy 600. The preferential dissolution of Ni and reduction of tetrathionate result in the formation of an oxide layer composed of Ni-depleted Cr-Fe oxides and Ni3S2 compounds.

引用

页码：9693 / 9702

页数：10

共 50 条

[21] Corrosion Behavior of Alloy 690 in Simulated Alkaline Water Chemistries Containing Sulfur at 300 °C
Xia Da-Hai
Luo Jing-Li
ACTA PHYSICO-CHIMICA SINICA, 2015, 31 (03) : 467 - 475
[22] Corrosion fatigue behavior of low alloy steels under simulated BWR coolant conditions
Huang, J. Y.
Young, M. C.
Jeng, S. L.
Yeh, J. J.
Huang, J. S.
Kuo, R. C.
JOURNAL OF NUCLEAR MATERIALS, 2010, 405 (01) : 17 - 27
[23] Stress corrosion cracking of alloy 600 and alloy 690 in hydrogen/steam and PWR primary side water
Sui, G
Heys, GB
Congleton, J
PROCEEDINGS OF THE EIGHTH INTERNATIONAL SYMPOSIUM ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOLS 1 AND 2, 1997, : 274 - 281
[24] Effect of nickel on the oxidation behavior of FeCrAl alloy in simulated PWR and BWR conditions
Qu, Haozheng J.
Abouelella, Hamdy
Chikhalikar, Atharva S.
Rajendran, Rupesh
Roy, Indranil
Priedeman, Jonathan
Umretiya, Rajnikant
Hoffman, Andrew
Wharry, Janelle. P.
Rebak, Raul
CORROSION SCIENCE, 2023, 216
[25] Effects of Cold-Work Degree on Stress Corrosion Cracking Behavior of Alloy 600 in Simulated Boiling Water Reactor (BWR) Water Environments
Lu, Wen-Feng
Huang, Jiunn-Yuan
Chen, Tai-Cheng
Tsai, Kun-Chao
CORROSION, 2020, 76 (10) : 930 - 940
[26] Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment
Lim, Yun Soo
Kim, Sung Woo
Hwang, Seong Sik
Kim, Hong Pyo
Jang, Changheui
CORROSION SCIENCE, 2016, 108 : 125 - 133
[27] Influence of Ethanolamine on Corrosion of Alloy 690 in Simulated Secondary Water
Wang, Jiazhen
Wang, Jianqiu
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2015, 31 (10) : 1039 - 1046
[28] Influence of Ethanolamine on Corrosion of Alloy 690 in Simulated Secondary Water
Jiazhen Wang
Jianqiu Wang
Journal of Materials Science & Technology, 2015, 31 (10) : 1039 - 1046
[29] Zinc treatment effects on corrosion behavior of Alloy 600 in high temperature, hydrogenated water
Ziemniak, Stephen E.
Hanson, Michael
CORROSION SCIENCE, 2006, 48 (10) : 3330 - 3348
[30] RELATION OF TUBE MANUFACTURING VARIABLES TO CORROSION AND CORROSION PRODUCT RELEASE RATES OF INCONEL 600 IN A SIMULATED PWR PRIMARY WATER
BODINE, GC
CARTER, JW
MATERIALS PERFORMANCE, 1975, 14 (11) : 22 - 28

← 1 2 3 4 5 →