Unveiling the synergistic effect of thermal aging and irradiation corrosion on the passivation performance and stress corrosion cracking of 308 L stainless steel under high-temperature water environment

被引:2
作者
Xi, Kai [1 ]
Qi, Wenlong [1 ]
Li, Yuanfei [2 ]
Zhao, Yang [1 ]
Liu, Xiangbing [3 ]
Zhang, Tao [1 ]
Wang, Fuhui [1 ]
机构
[1] Northeastern Univ, Corros & Protect Ctr, Shenyang 110819, Peoples R China
[2] Suzhou Nucl Power Res Inst, Mat Engn Technol Ctr, Suzhou 215004, Peoples R China
[3] Natl Engn Res Ctr Nucl Power Plant Safety & Reliab, Suzhou 215004, Peoples R China
基金
中国国家自然科学基金;
关键词
Thermal aging; Irradiation; 308 L stainless steel; Stress corrosion cracking; MECHANICAL-PROPERTIES; G-PHASE; MICROSTRUCTURAL EVOLUTION; SPINODAL DECOMPOSITION; LOCALIZED DEFORMATION; PITTING CORROSION; CAST; REACTOR; FERRITE; PRESSURE;
D O I
10.1016/j.matchar.2024.114445
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This study investigated coupling of thermal aging with irradiation corrosion, and carried out the microstructure and electrochemical characterization of 308 L stainless steel (SS). The passivation performance of 308 L SS was studied under the simulated pressurized water reactor (PWR) environmental condition and its stress corrosion cracking (SCC) performance was tested under thermal aging-irradiation conditions. The experimental results indicate that thermal aging results in spinodal decomposition of delta-ferrite, giving rise to G-phase precipitate and carbide precipitate formation at delta/gamma-phase interface, whereas irradiation causes Cr depletion and Ni enrichment at the interface. Both thermal aging and irradiation lead to the decreased corrosion resistance of 308 L SS. Under coupling conditions of the two, severe Cr loss occurs at the phase boundary, which leads to severe corrosion on delta/gamma phase boundary and also reduces SCC resistance of 308 L SS.
引用
收藏
页数:18
相关论文
共 64 条
[1]  
Bjurman M., 2015, 17 INT C ENV DEGR MA, P1
[2]   Role of irradiation and irradiation defects on the oxidation first stages of a 316L austenitic stainless steel [J].
Boisson, M. ;
Legras, L. ;
Andrieu, E. ;
Laffont, L. .
CORROSION SCIENCE, 2019, 161
[3]   Low temperature thermal aging of austenitic stainless steel welds: Kinetics and effects on mechanical properties [J].
Chandra, K. ;
Kain, Vivekanand ;
Bhutani, Vikas ;
Raja, V. S. ;
Tewari, R. ;
Dey, G. K. ;
Chakravartty, J. K. .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2012, 534 :163-175
[4]   Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water [J].
Chen, Junjie ;
Jang, Changheui ;
Kong, Byeon Seo ;
Xiao, Qian ;
Subramanian, Gokul Obulan ;
Kim, Ho Sub ;
Shin, Ji Ho .
CORROSION SCIENCE, 2020, 172
[5]   Evaluation of pitting corrosion in duplex stainless steel Fe20Cr9Ni for nuclear power application [J].
Chen, Yuefeng ;
Yang, Bin ;
Zhou, Yangtao ;
Wu, Yuan ;
Zhu, Huihui .
ACTA MATERIALIA, 2020, 197 :172-183
[6]   Pitting behavior of thermally aged Z3CN20.09M cast stainless steel for primary coolant pipe of nuclear power plant [J].
Chen, Yuefeng ;
Chen, Bo ;
Dong, Fang ;
Yang, Bin ;
Li, Shilei ;
Yu, Xiaoyi .
ENGINEERING FAILURE ANALYSIS, 2018, 83 :1-8
[7]  
Chopra O.K., 1987, P 3 C ENV DEGR MAT N
[8]  
CHUNG HM, 1990, MATER SCI TECH SER, V6, P249, DOI 10.1179/026708390790191170
[9]   Atom probe studies of the Fe-Cr system and stainless steels aged at intermediate temperature: A review [J].
Danoix, F ;
Auger, P .
MATERIALS CHARACTERIZATION, 2000, 44 (1-2) :177-201
[10]  
David S.A., 1996, J. Nondestruct. Eval, V15, P129, DOI [10.1007/BF00732040, DOI 10.1007/BF00732040]