Please wait a minute...
Just Accepted | Current Issue | Archive | Featured Articles | Special Issue | Most Read | Most Downloaded | Most Cited
Journal of Chinese Society for Corrosion and protection  2021, Vol. 41 Issue (4): 417-428    DOI: 10.11902/1005.4537.2020.101
Current Issue | Archive | Adv Search |
Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water
JIAO Yang, ZHANG Shenghan(), TAN Yu
Department of Environment Science and Engineering, North China Electric Power University, Baoding 071003, China
Download:  HTML  PDF(2782KB) 
Export:  BibTeX | EndNote (RIS)      
Abstract  

Stress corrosion cracking behavior (SCC) of typical nuclear structural materials stainless steel in high-temperature and high-pressure water was reviewed. The effect of material type, mechanical properties, water chemistry on the sensitivity, initiation and propagation of cracks were discussed. The development of the zinc injection technology in the coolant system and its inhibitory effect on the primary side stress corrosion (PWSCC) were introduced. Finally, by taking various factors and actual operating conditions into consideration, the method of reducing the sensitivity of SCC was summarized, and the problems that should be focused on in future research were proposed.
Key words:  nuclear power plant      stainless steel      SCC      zing injection technology     
Received:  12 June 2020     
ZTFLH:  TG174  
Corresponding Authors:  ZHANG Shenghan     E-mail:  shenghan_zhang@126.com
About author:  ZHANG Shenghan, E-mail: shenghan_zhang@126.com
Service
E-mail this article
Add to citation manager
E-mail Alert
RSS
（）
Articles by authors
Yang JIAO
Shenghan ZHANG
Yu TAN

Cite this article: 

JIAO Yang, ZHANG Shenghan, TAN Yu. Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water. Journal of Chinese Society for Corrosion and protection, 2021, 41(4): 417-428.

URL: 

https://www.jcscp.org/EN/10.11902/1005.4537.2020.101     OR     https://www.jcscp.org/EN/Y2021/V41/I4/417

Fig.1  Effects of yield strength on crack growth rate of stainless steels[15,29]
Fig.2  Variations of crack growth rates of several stainless steels in oxygenated pure water at high temperature with stress intensity factor[32,33]
Fig.3  Effects of temperature, heat treatment and surface state on stress corrosion cracking of 304 stainless steel[44]
Fig.4  Effects of pH on SCC of 304L, 316L and France Z6CND17.12 austenitic stainless steel[47-49]
ParameterAP1000Qinshan nuclear power Plant
Conductivity1~40 μS/cm (25 ℃)1~40 μS/cm (25 ℃)
pH4.2~10.5 (25 ℃)5.4~10.5 (25 ℃)
O2≤0.1 mg/L≤0.1 mg/L
Cl-≤0.15 mg/L≤0.1 mg/L
F-≤0.15 mg/L---
H225~50 cm3 (STP)/kg H2O25~35 cm3 (STP)/kg H2O
Suspended solids≤0.2 mg/L≤1.0 mg/L
LiOH---0.22~2.2 mg/L
H3BO30~4000 mg/L (calculated as B)0~2400 mg/L (calculated as B)
Table 1  Water quality requirements for PWR primary water
1 Tang W. Analysis of fracture parameters on stress corrosion cracking of structural material in nuclear power plants under micro-scale [D]. Xi'an: Xi'an University of Science and Technology, 2012
唐伟. 微观尺度下核电结构材料应力腐蚀裂纹断裂参量分析 [D]. 西安: 西安科技大学, 2012
2 Sun H T, Ling L G, Lv Y H, et al. Stress corrosion problems and safety management of equipment materials for domestic pressurized water reactor nuclear power station [J]. Corros. Sci. Prot. Technol., 2016, 28: 283
孙海涛, 凌礼恭, 吕云鹤等. 国内压水堆核电站设备材料应力腐蚀问题及安全管理 [J]. 腐蚀科学与防护技术, 2016, 28: 283
3 Couvant T, Moulart P, Legras L, et al. PWSCC of austenitic stainless steels of heaters of pressurizers [A]. Proceedings of the 13th International Conference on Environment Degradation of Materials in Nuclear Power Systems Water Reactors [C]. British Columbia (Canada), 2007
4 Couvant T, Legras L, Vaillant F, et al. Effect of strain-hardening on stress corrosion cracking of AISI 304L stainless steel in PWR primary environment at 360 ℃ [A]. 12th International Conference on Environmental Degradation of Materials in Nuclear Power System [C]. Salt Lake City (US), 2005
5 Li B. The microstructure and stress corrosion cracking behavior study of nuclear plant 304 stainless steel welded joints [D]. Tianjin: Tianjin University, 2015
李博. 核电站用304不锈钢焊接接头组织和应力腐蚀行为研究 [D]. 天津: 天津大学, 2015
6 Ma C, Peng Q J, Han E-H, et al. Review of stress corrosion cracking of structural materials in nuclear power plants [J]. J. Chin. Soc. Corros. Prot., 2014, 34: 37
马成, 彭群家, 韩恩厚等. 核电结构材料应力腐蚀开裂的研究现状与进展 [J]. 中国腐蚀与防护学报, 2014, 34: 37
7 Dang H Y, Zhang Y J, Luo X F, et al. Comparison and application of common stress corrosion standard test methods [J]. Phys. Test. Chem. Anal., 2018, 54A: 672
党恒耀, 张亚军, 罗先甫等. 常见应力腐蚀标准试验方法对比及应用 [J]. 理化检验 (物理分册), 2018, 54A: 672
8 Zhang Z, Wu X Q, Tan J B. Review of electrochemical noise technique for in situ monitoring of stress corrosion cracking [J]. J. Chin. Soc. Corros. Prot., 2020, 40: 223
张震, 吴欣强, 谭季波. 电化学噪声原位监测应力腐蚀开裂的研究现状与进展 [J]. 中国腐蚀与防护学报, 2020, 40: 223
9 Scenini F, Lindsay J, Chang L T, et al. Oxidation and SCC initiation studies of type 304L SS in PWR primary water [A]. Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors [C]. Oregon (USA), 2018: 793
10 Peyre P, Scherpereel X, Berthe L, et al. Surface modifications induced in 316L steel by laser peening and shot-peening. Influence on pitting corrosion resistance [J]. Mater. Sci. Eng., 2000, A280: 294
11 Zhu C H, Lu Z M, Gao H G. Influence of shot peening pressure on stress corrosion susceptibility of 304 stainless steel [J]. Heat Treat. Met., 2011, 36(10): 42
朱成辉, 卢志明, 高红刚. 表面喷丸压力对304不锈钢应力腐蚀敏感性的影响 [J]. 金属热处理, 2011, 36(10): 42
12 Wu S H, Huang K F, Hu J L, et al. Study on the application of laser-peening technique for nuclear power equipment [J]. China Nucl. Power, 2011, 4: 207
吴树辉, 黄科峰, 胡金力等. 激光喷丸技术在核电设备上的应用 [J]. 中国核电, 2011, 4: 207
13 Milad M, Zreiba N, Elhalouani F, et al. The effect of cold work on structure and properties of AISI 304 stainless steel [J]. J. Mater. Process. Technol., 2008, 203: 80
14 Kuniya J, Masaoka I, Sasaki R. Effect of cold work on the stress corrosion cracking of nonsensitized AISI 304 stainless steel in high-temperature oxygenated water [J]. Corrosion, 1988, 44: 21
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: 1114
16 Liu X L, Hwang W, Park J, et al. Toward the multiscale nature of stress corrosion cracking [J]. Nucl. Eng. Technol., 2018, 50: 1
17 Zhang L T. Research on stress corrosion crack growth behavior of nuclear grade 316 stainless steel in high temperature and high pressure water environment [D]. Beijing: University of Chinese Academy of Sciences, 2014
张利涛. 核级316不锈钢在高温高压水环境中的应力腐蚀裂纹扩展行为研究 [D]. 北京: 中国科学院大学, 2014
18 Arioka K, Yamada T, Terachi T, et al. Dependence of stress corrosion cracking for cold-worked stainless steel on temperature and potential, and role of diffusion of vacancies at crack tips [J]. Corrosion, 2008, 64: 691
19 Terachi T, Yamada T, Miyamoto T, et al. SCC growth behaviors of austenitic stainless steels in simulated PWR primary water [J]. J. Nucl. Mater., 2012, 426: 59
20 Shoji T, Li G, Kwon J, et al. Quantification of yield strength effects on IGSCC of austenitic stainless steels in high temperature water [A]. Proceedings of the 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems [C]. Warrendale, PA, 2003: 834
21 Meng F J, Lu Z P, Shoji T, et al. Stress corrosion cracking of uni-directionally cold worked 316NG stainless steel in simulated PWR primary water with various dissolved hydrogen concentrations [J]. Corros. Sci., 2011, 53: 2558
22 Hong H U, Nam S W. The occurrence of grain boundary serration and its effect on the M23C6 carbide characteristics in an AISI 316 stainless steel [J]. Mater. Sci. Eng., 2002, A332: 255
23 Sahlaoui H, Makhlouf K, Sidhom H, et al. Effects of ageing conditions on the precipitates evolution, chromium depletion and intergranular corrosion susceptibility of AISI 316L: Experimental and modeling results [J]. Mater. Sci. Eng., 2004, A372: 98
24 Sun X Y, Liu X G, Wang L L, et al. Influence of solution annealing on intergranular corrosion resistance of 316L stainless steel [J]. Corros. Sci. Prot. Technol., 2014, 26: 228
孙小燕, 刘孝光, 汪列隆等. 固溶处理对316L不锈钢晶间腐蚀性能的影响 [J]. 腐蚀科学与防护技术, 2014, 26: 228
25 Li G F, Huang Z Y, Huang C B, et al. Electrochemical behavior and stress corrosion cracking behavior of stainless steel for internal components in high temperature and high pressure water environment [A]. Proceedings of the 2006 National Nuclear Materials Academic Exchange Conference [C]. Chengdu, 2006: 100
李光福, 黄中艺, 黄春波等. 堆内构件用不锈钢在高温高压水环境中的电化学行为与应力腐蚀破裂行为 [A]. 2006全国核材料学术交流会论文集 [C]. 成都, 2006: 100
26 Kamaya M. Influence of bulk damage on crack initiation in low-cycle fatigue of 316 stainless steel [J]. Fatigue Fract. Eng. Mater. Struct., 2010, 33: 94
27 Kamaya M, Haruna T. Crack initiation model for sensitized 304 stainless steel in high temperature water [J]. Corros. Sci., 2006, 48: 2442
28 Kamaya M. Environmental effect on fatigue strength of stainless steel in PWR primary water-role of crack growth acceleration in fatigue life reduction [J]. Int. J. Fatigue, 2013, 55: 102
29 Ru X, Staehle R W. Historical experience providing bases for predicting corrosion and stress corrosion in emerging supercritical water nuclear technology-part 2: Review [J]. Corrosion, 2013, 69: 319
30 Lu Z P, Shoji T, Meng F J, et al. Effects of water chemistry and loading conditions on stress corrosion cracking of cold-rolled 316NG stainless steel in high temperature water [J]. Corros. Sci., 2011, 53: 247
31 Gavrilov S, Vankeerberghen M, Nelissen G, et al. Finite element calculation of crack propagation in type 304 stainless steel in diluted sulphuric acid solutions [J]. Corros. Sci., 2007, 49: 980
32 Itow M, Kikuchi N, Tanka J, et al. SCC growth rates and reference curves for low carbon stainless steels in BWR environments [A]. Proceedings of the ASME/JSME 2004 Pressure Vessels and Piping Conference [C]. San Diego, California, USA, 2004: 167
33 Tsubota M, Katayama Y, Saito Y. Stress corrosion crack growth behavior of cold worked austenitic stainless steel in high temperature water [A]. Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors [C]. Salt Lake City, UT, United States, 2005: 109
34 Andresen P L, Ford F P. Fundamental modeling of environmental cracking for improved design and lifetime evaluation in BWRs [J]. Int. J. Pressure Vessels Pip., 1994, 59: 61
35 Andresen P L, Ford F P. Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems [J]. Mater. Sci. Eng., 1988, A103: 167
36 Han E-H, Wang J Q, Wu X Q, et al. Corrosion mechanisms of stainless steel and nickel base alloys in high temperature high pressure water [J]. Acta Metall. Sin., 2010, 46: 1379
韩恩厚, 王俭秋, 吴欣强等. 核电高温高压水中不锈钢和镍基合金的腐蚀机制 [J]. 金属学报, 2010, 46: 1379
37 Ford F P. Mechanisms of environmental cracking in systems peculiar to the power generation industry [R]. EPRI Contract RP1332-1, EPRI Report NP-2589, 1982
38 Ford F P, Povich M J. The effect of oxygen temperature combinations on the stress corrosion susceptibility of sensitized type 304 stainless steel in high purity water [J]. Corrosion, 1979, 35: 569
39 Agrawal A K, Welch G A, Begley J A, et al. Stress corrosion of sensitized and quench annealed type 304 stainless steels in high purity water [A]. Corrosion/78 [C]. Houston, 1978: 187
40 White E L, Berry W E. Influence of cyclic load and environmental effects on stress corrosion cracking of sensitized stainless steel. Final report [R]. 1981
41 Hale D A. The effect of BWR startup environments on crack growth in structural alloys [J]. J. Eng. Mater. Technol., 1986, 108: 44
42 Andresen P. L.Effects of Temperature on Crack Growth Rate in Sensitized Type304Stainless Steel and Alloy 600 [J]. Corrosion Science, 1993, 49(9): 714
43 Ruther W E, Soppet W K, Kassner T F. Effect of temperature and ionic impurities at very low concentrations on stress corrosion cracking of AISI 304 stainless steel [J]. Corrosion, 1988, 44: 791
44 Andresen P L. Crack initiation in CERT tests on type 304 stainless steel in pure water [J]. Corrosion, 1982, 38: 53
45 Li N. Influence of water chemistry on corrosion behavior of 304 stainless steel in high temperature-high pressure solution [D]. Tianjin: Tianjin University, 2012
李娜. 高温高压水介质对304不锈钢腐蚀性能的影响研究 [D]. 天津: 天津大学, 2012
46 Guan J X, Li Y, Dong C F, et al. Effect of temperature on stress corrosion cracking of 316L stainless steel in high-temperature water [J]. J. Univ. Sci. Technol. Beijing, 2009, 31: 1122
关矞心, 李岩, 董超芳等. 高温水环境下温度对316L不锈钢应力腐蚀开裂的影响 [J]. 北京科技大学学报, 2009, 31: 1122
47 Xu C L, Zhang L, Qian W J, et al. Influence factors of stress corrosion cracking in stainless steel for reactor internals [J]. China Metall., 2016, 26(6): 37
徐超亮, 张路, 钱王洁等. 堆内构件用不锈钢应力腐蚀开裂的影响因素 [J]. 中国冶金, 2016, 26(6): 37
48 Dong C F, Guan J X, Cheng X Q, et al. Effects of pH values on the stress corrosion cracking of 304L stainless steel in high-temperature and high-pressure water [J]. J. Univ. Sci. Technol. Beijing, 2010, 32: 1569
董超芳, 关矞心, 程学群等. pH值对高温高压水中304L不锈钢应力腐蚀开裂的影响 [J]. 北京科技大学学报, 2010, 32: 1569
49 Guan J X. Study on stress corrosion cracking of stainless steel in acid and alkali solution under high temperature [J]. Total Corros. Control, 2016, 30(9): 63
关矞心. 316L不锈钢在高温酸碱溶液中的应力腐蚀行为 [J]. 全面腐蚀控制, 2016, 30(9): 63
50 Li H M, Yang W, Cai X, et al. Fractography of the stress corrosion cracking specimens of type 304 stainless steel in high temperature water containing boric acid and lithium ion [J]. J. Chin. Soc. Corros. Prot., 2004, 24: 16
李红梅, 杨武, 蔡珣等. 304不锈钢在含硼和锂的高温水中的应力腐蚀破裂和断口分析 [J]. 中国腐蚀与防护学报, 2004, 24: 16
51 Li H M, Cai X, Lv Z P, et al. Analysis of surface oxide films on stress corrosion cracking specimens of type 304 stainless steel in high temperature water containing boric acid and lithium ion [J]. J. Mater. Eng., 2004, (4): 7
李红梅, 蔡珣, 吕战鹏等. 304不锈钢在含硼和锂的高温水中的应力腐蚀破裂和表层氧化膜分析 [J]. 材料工程, 2004, (4): 7
52 Ehrlich K, Konys J, Heikinheimo L. Materials for high performance light water reactors [J]. J. Nucl. Mater., 2004, 327: 140
53 Yang W, Zhao G Z, Zhang M J, et al. An AES investigation of the surface films formed on stress corrosion test specimens of type 304 stainless steel in high temperature water [J]. Corros. Sci., 1992, 33: 89
54 Congleton J, Zheng W, Hua H. Stress corrosion cracking of annealed type 316 stainless steel in high-temperature water [J]. Corrosion, 1990, 46: 621
55 Li G F, Congleton J. Stress corrosion cracking of a low alloy steel to stainless steel transition weld in PWR primary waters at 292°C [J]. Corros. Sci., 2000, 42: 1005
56 Du D H. Stress corrosion cracking study of 316 stainless steel in PWR primary water conditions [D]. Shanghai: Shanghai Jiaotong University, 2014
杜东海. 316不锈钢在压水堆一回路环境下的应力腐蚀性能研究 [D]. 上海: 上海交通大学, 2014
57 Peng Q J, Li G F, Shoji T. The crack tip solution chemistry in sensitized stainless steel in simulated boiling water reactor water studied using a microsampling technique [J]. J. Nucl. Sci. Technol., 2003, 40: 397
58 Vermilyea D A. A theory for the propagation of stress corrosion cracks in metals [J]. J. Electrochem. Soc., 1972, 119: 405
59 Turnbull A. Modelling of environment assisted cracking [J]. Corros. Sci., 1993, 34: 921
60 Ford F P. Quantitative prediction of environmentally assisted cracking [J]. Corrosion, 1996, 52: 375
61 Zhang K Q, Hu S L, Tang Z M, et al. Review on stress corrosion crack propagation behavior of cold worked nuclear structural materials in high temperature and high pressure water [J]. J. Chin. Soc. Corros. Prot., 2018, 38: 517
张克乾, 胡石林, 唐占梅等. 冷加工核电结构材料在高温高压水中应力腐蚀裂纹扩展行为的研究进展 [J]. 中国腐蚀与防护学报, 2018, 38: 517
62 MacDonald D D, Urquidi-MacDonald M. A coupled environment model for stress corrosion cracking in sensitized type 304 stainless steel in LWR environments [J]. Corros. Sci., 1991, 32: 51
63 MacDonald D D, Lu P C, Urquidi-MacDonald M D, et al. Theoretical estimation of crack growth rates in type 304 stainless steel in boiling-water reactor coolant environments [J]. Corrosion, 1996, 52: 768
64 Shi J B. Prediction of stress corrosion crack growth rate in nuclear power plant structural materials [D]. Tianjin: Tianjin University, 2014
石江波. 核电结构材料应力腐蚀开裂裂纹扩展速率预测 [D]. 天津: 天津大学, 2014
65 Wood C J, Marble W J, Prystupa M, et al. Experience with zinc injection passivation at BWR plants in the USA [J]. Water chemistry of nuclear reactor systems 5, 1989
66 Lister D H, Godin M S. The effect of dissolved zinc on the transport of corrosion products in PWRs [R]. Palo Alto, CA(USA): Electric Power Research Institute, 1990
67 Jiang S Q. The effects of zinc injection of corrosion behaviors of PWR primary loop structural materials [D]. Shanghai: Shanghai Jiaotong University, 2011
姜苏青. 注锌对压水堆核电站一回路结构材料腐蚀行为影响的研究 [D]. 上海: 上海交通大学, 2011
68 Jiang L. Research and application of zinc injection in PWRs [A]. Progress Report on China Nuclear Science & Technology (Vol. 2) [C]. Guiyang, 2011: 74
姜磊. 压水堆核电站加锌技术的研究与应用 [A]. 中国核科学技术进展报告 (第二卷) [C]. 贵阳, 2011: 74
69 Pathania R, Yagnik S, Gold R E, et al. Evaluation of zinc addition to PWR primary coolant [A]. NACE International [C]. Houston, TX (United States), 1995
70 Gold R E, Kormuth J W, Bergmann C A, et al. Evaluation of zinc addition to primary coolant of Farley-2 PWRs [R]. Palo Alto, CA: EPRI, 1996
71 Huang Y, Wu W S, Cong S, et al. Stress corrosion behaviors of 316LN stainless steel in a simulated PWR primary water environment [J]. Materials, 2018, 11: 1509
72 Zhang L F, Chen K, Wang J M, et al. Effects of zinc injection on stress corrosion cracking of cold worked austenitic stainless steel in high-temperature water environments [J]. Scr. Mater., 2017, 140: 50
73 Du D H, Chen K, Zhang L F, et al. Effect of zinc on stress corrosion crack growth rate of type 316 stainless steel [J]. Nucl. Power Eng., 2017, 38(2): 82
杜东海, 陈凯, 张乐福等. 注锌对316不锈钢应力腐蚀裂纹扩展速率的影响 [J]. 核动力工程, 2017, 38(2): 82
74 Liu X H. Study on corrosion behavior of nuclear grade stainless steel in high temperature and pressure water with zinc [D]. Shenyang, Institute of Metal Research, Chinese Academy of Sciences, 2014
刘侠和. 高温高压加锌水化学环境下核级不锈钢的腐蚀行为研究 [D]. 沈阳, 中国科学院金属研究所, 2014
75 Qiao P P, Zhang L F, Liu R Q, et al. Zinc addition effects on general corrosion of austenitic stainless steels in PWR primary conditions [J]. Atom. Energy Sci. Technol., 2010, 44: 690
乔培鹏, 张乐福, 刘瑞芹等. 压水堆条件下锌对奥氏体不锈钢腐蚀性能的影响 [J]. 原子能科学技术, 2010, 44: 690
76 Liu X H, Wu X Q, Han E-H. Effect of Zn injection on established surface oxide films on 316L stainless steel in borated and lithiated high temperature water [J]. Corros. Sci., 2012, 65: 136
77 Marks C, Dumouchel M, Reid R, et al. Quantifying the benefit of chemical mitigation of PWSCC via zinc addition or hydrogen optimization [A]. Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors [C]. Colorado, 2011: 1893
78 Norring K, Engström J. Initiation of SCC in nickel base alloys in primary PWR environment: studies at Studsvik since mid 1980s [J]. Energy Mater., 2008, 3: 113
79 Angeliu T M, Andresen P L. Effect of zinc additions on oxide rupture strain and repassivation kinetics of iron-based alloys in 288 ℃ water [J]. Corrosion, 1996, 52: 28
80 Lin C C. A review of corrosion product transport and radiation field buildup in boiling water reactors [J]. Prog. Nucl. Energy, 2009, 51: 207
81 Lister D H. Mechanisms of zinc interaction with oxide films in high-temperature water [A]. Presentation at EPRI Meeting [C]. Toronto, Ontario, Canada, 2004
82 Tian F L, Ma X L. Analysis the application of zinc injection in nuclear power plant [J]. Shanxi Chem. Ind., 2016, 36(2): 70
田风龙, 马秀玲. 浅析加锌技术在核电厂的应用 [J]. 山西化工, 2016, 36(2): 70
[1] RAN Dou, MENG Huimin, LI Quande, GONG Xiufang, NI Rong, JIANG Ying, GONG Xianlong, DAI Jun, LONG Bin. Effect of Temperature on Corrosion Behavior of 14Cr12Ni3-WMoV Stainless Steel in 0.02 mol/L NaCl Solution[J]. 中国腐蚀与防护学报, 2021, 41(3): 362-368.
[2] LIU Xinyi, ZHAO Yazhou, ZHANG Huan, CHEN Li. Effect of Chloride Concentration in a Simulated Concrete Pore Solution on Metastable Pitting of 304 Stainless Steel[J]. 中国腐蚀与防护学报, 2021, 41(2): 195-201.
[3] ZHANG Huiyun, ZHENG Liuwei, MENG Xianming, LIANG Wei. Effect of Electrochemical Hydrogen Charging on Hydrogen Embrittlement Sensitivity of Cr15 Ferritic and 304 Austenitic Stainless Steels[J]. 中国腐蚀与防护学报, 2021, 41(2): 202-208.
[4] ZUO Yong, CAO Mingpeng, SHEN Miao, YANG Xinmei. Effect of Mg on Corrosion of 316H Stainless Steel in Molten Salts MgCl2-NaCl-KCl[J]. 中国腐蚀与防护学报, 2021, 41(1): 80-86.
[5] RAN Dou, MENG Huimin, LIU Xing, LI Quande, GONG Xiufang, NI Rong, JIANG Ying, GONG Xianlong, DAI Jun, LONG Bin. Effect of pH on Corrosion Behavior of 14Cr12Ni3WMoV Stainless Steel in Chlorine-containing Solutions[J]. 中国腐蚀与防护学报, 2021, 41(1): 51-59.
[6] WANG Xintong, CHEN Xu, HAN Zhenze, LI Chengyuan, WANG Qishan. Stress Corrosion Cracking Behavior of 2205 Duplex Stainless Steel in 3.5%NaCl Solution with Sulfate Reducing Bacteria[J]. 中国腐蚀与防护学报, 2021, 41(1): 43-50.
[7] MA Mingwei, ZHAO Zhihao, JING Siwen, YU Wenfeng, GU Yien, WANG Xu, WU Ming. Corrosion Behavior of 17-4 PH Stainless Steel in Simulated Seawater Containing SRB[J]. 中国腐蚀与防护学报, 2020, 40(6): 523-528.
[8] ZHANG Hao, DU Nan, ZHOU Wenjie, WANG Shuaixing, ZHAO Qing. Effect of Fe3+ on Pitting Corrosion of Stainless Steel in Simulated Seawater[J]. 中国腐蚀与防护学报, 2020, 40(6): 517-522.
[9] LI Qing, ZHANG Deping, WANG Wei, WU Wei, LU Lin, AI Chi. Evaluation of Actual Corrosion Status of L80 Tubing Steel and Subsequent Electrochemical and SCC Investigation in Lab[J]. 中国腐蚀与防护学报, 2020, 40(4): 317-324.
[10] ZHAO Baijie, FAN Yi, LI Zhenzhen, ZHANG Bowei, CHENG Xuequn. Crevice Corrosion Behavior of 316L Stainless Steel Paired with Four Different Materials[J]. 中国腐蚀与防护学报, 2020, 40(4): 332-341.
[11] HU Yuting, DONG Pengfei, JIANG Li, XIAO Kui, DONG Chaofang, WU Junsheng, LI Xiaogang. Corrosion Behavior of Riveted Joints of TC4 Ti-Alloy and 316L Stainless Steel in Simulated Marine Atmosphere[J]. 中国腐蚀与防护学报, 2020, 40(2): 167-174.
[12] QIN Yueqiang, ZUO Yong, SHEN Miao. Corrosion Inhibition of 316L Stainless Steel in FLiNaK-CrF3/CrF2 Redox Buffering Molten Salt System[J]. 中国腐蚀与防护学报, 2020, 40(2): 182-190.
[13] HE Zhuang,WANG Xingping,LIU Zihan,SHENG Yaoquan,MI Mengxin,CHEN Lin,ZHANG Yan,LI Yuchun. Passivation and Pitting of 316L and HR-2 Stainless Steel in Hydrochloric Acid Liquid Membrane Environment[J]. 中国腐蚀与防护学报, 2020, 40(1): 17-24.
[14] WU Dongcai,HAN Peide. Effects of Moderate Temperature Aging Treatment on Corrosion Resistance of SAF2304 DuplexStainless Steel[J]. 中国腐蚀与防护学报, 2020, 40(1): 51-56.
[15] FU Anqing,ZHAO Mifeng,LI Chengzheng,BAI Yan,ZHU Wenjun,MA Lei,XIONG Maoxian,XIE Junfeng,LEI Xiaowei,LV Naixin. Effect of Laser Surface Melting on Microstructure and Performance of Super 13Cr Stainless Steel[J]. 中国腐蚀与防护学报, 2019, 39(5): 446-452.
No Suggested Reading articles found!

Copyright © 2017 Journal of Chinese Society for Corrosion and protection, All Rights Reserved.
Editorial Office: Journal of Chinese Society for Corrosion and Protection, 72 Wenhua Rd., Shenyang 110016, China
Tel: +86- 024-23971318, Fax: +86-024-23971819 　E-mail: jcscp@imr.ac.cn
Powered by Beijing Magtech