Review on Stress Corrosion Crack Propagation Behavior of Cold Worked Nuclear Structural Materials in High Temperature and High Pressure Water

doi:10.11902/1005.4537.2017.165

Journal of Chinese Society for Corrosion and protection

2018, Vol. 38

Issue (6): 517-522 DOI: 10.11902/1005.4537.2017.165

Current Issue | Archive | Adv Search

Review on Stress Corrosion Crack Propagation Behavior of Cold Worked Nuclear Structural Materials in High Temperature and High Pressure Water

Keqian ZHANG,Shilin HU(

),Zhanmei TANG,Pingzhu ZHANG

1. China Institute of Atomic Energy, Beijing 102413, China

Download:

HTML

PDF(1245KB)
Export: BibTeX | EndNote (RIS)

Abstract

The influence of cold work on the stress corrosion cracking (SCC), namely the crack growth rate (CGR) and the crack propagation orientations of the nuclear structural materials and especially the effect of temperature on the stress corrosion cracking, of the cold-worked steels and nickel base alloys were summarized. The effect cold-working processing on the SCC sensitivity was analyzed. The future trends of R&D in the field was also expounded. The cold rolling process induced elongated grains along the rolling direction, and the lamellar-like local strain areas generated at grain boundaries. Some deformation bands and a large number of dislocations and vacancies are formed inside the grain due to cold rolling, resulting in the increase of the stress corrosion cracking CGR. The localized oxidation of the grain deformation bands will affect the type of stress corrosion and the direction of crack propagation. The movement of defects at different temperatures will change the CGR of cracks. The future research should focus on the mechanism of stress corrosion cracking of old worked materials and the SCC behavior of cold-worked materials under actual service conditions.

Key words: cold worked stress corrosion cracking crack growth rate local strain vacancy defect

Received: 11 October 2017

ZTFLH:

TG172.5

Corresponding Authors: Shilin HU E-mail: husl@ciae.cn

	Service

	E-mail this article
	Add to citation manager
	E-mail Alert
	RSS
	（）
	Articles by authors
	Keqian ZHANG
	Shilin HU
	Zhanmei TANG
	Pingzhu ZHANG

Cite this article:

Keqian ZHANG,Shilin HU,Zhanmei TANG,Pingzhu ZHANG. Review on Stress Corrosion Crack Propagation Behavior of Cold Worked Nuclear Structural Materials in High Temperature and High Pressure Water. Journal of Chinese Society for Corrosion and protection, 2018, 38(6): 517-522.

URL:

https://www.jcscp.org/EN/10.11902/1005.4537.2017.165 OR https://www.jcscp.org/EN/Y2018/V38/I6/517

Fig.1 Schematic illustration of the relationship of rolling orientation with the longitudinal (L), thickness (T) and short transverse (S) directions^[26]

Fig.2 Illustration of SCC growth behavior at the crack tip of coldworked 304LSS^[35]

Fig.3 SCC growth ratevstemperature curves for CW316 SS in high-temperature water^[20,36,37]

Fig.4 SCC growth ratevstemperature curves for CW 690 alloy in high-temperature water^[22]

[1]	Tsubota M,Kanazawa Y,Inoue H.The effect of cold worked on the SCC susceptibility of austenitic stainless steels[A].Proceedings of the 7th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactor[C].Breckenridge Colorado,1995:519
[2]	Kanazawa Y,Tsubota M.Stress corrosion cracking of cold worked stainless steel in high temperature water[R].Houston, TX, United States:NACE International,1994
[3]	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(1-3):80
[4]	Berge P,Donati J R,Prieux B,et al.Caustic stress corrosion of Fe-Cr-Ni austenitic alloys[J].Corrosion,1977,33:425
[5]	Korostelev A B,Abramov V Y,Belous V N.Evaluation of stainless steels for their resistance to intergranular corrosion[J]. J. Nucl. Mater.,1996,233-237:1361
[6]	Lisowyj B.Evaluation of cracking in type 348 stainless steel control element drive mechanism housings[A].Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C].San Diego, California,1993:343
[7]	Peng Q J,Hou J,Yonezawa T,et al.Environmentally assisted crack growth in one-dimensionally cold worked Alloy 690TT in primary water[J].Corros. Sci.,2012,57:81
[8]	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
[9]	Wang S,Takeda Y,Sakaguchi K,et al.Cracking paths during initiation of environmentally assisted cracking in high temperature water[J]. J Nucl. Sci. Technol.,2005,42(7):670
[10]	Yaguchi S,Yonezawa T.Intergranular Stress Corrosion Cracking growth perpendicular to fatigue pre-cracks in T-L oriented compact tension specimens in simulated Pressurized Water Reactor primary water[J].Corros. Sci.,2014,86:326
[11]	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
[12]	Barton G B.Influence of container material on character of corrosion products produced on austenitic stainless steels by hot concentrated sodium hydroxide[J].Scr. Metall.,1977,11:391
[13]	Agrawal A K,Sheth K G,Poteet K,et al.The polarization behavior of Fe-Ni-Cr alloys in concentrated sodium hydroxide solutions in the temperature range 25 ℃ to 150 ℃[J]. J. Electrochem. Soc.,1972,119:1637
[14]	Zhang W G,Gao F Q,Zhou H Y.Stress corrosion cracking of steam generator tube and primary pipe in PWR type nuclear power plants[J].Atom. Energy Sci. Technol.,1993,27:367
[14]	张伟国,高凤琴,周洪毅.PWR核电站蒸汽发生器传热管和主管道的应力腐蚀破裂研究[J].原子能科学技术,1993,27:367
[15]	Xie X F,Ning D,Chen B,et al.Stress corrosion cracking behavior of cold-drawn 316 austenitic stainless steels in simulated PWR environment[J].Corros. Sci.,2016,112:576
[16]	Lozano-Perez S,Yamada T,Terachi T,et al.Multi-scale characterization of stress corrosion cracking of cold-worked stainless steels and the influence of Cr content[J].Acta Mater.,2009,57:5361
[17]	Staehle R W,Royuela J J,Raredon T L,et al.Effect of alloy composition on stress corrosion cracking of Fe-Cr-Ni base alloys[J].Corrosion,1970,26:451
[18]	Arioka K,Miyamoto T,Yamada T,et al.Formation of cavities prior to crack initiation and growth on cold-worked carbon steel in high-temperature water[J].Corrosion,2010,66:015008
[19]	Arioka K,Miyamoto T,Yamada T,et al.Formation of cavities prior to crack initiation and growth on cold-worked carbon steel in high-temperature water[J].Corrosion,2010,66(1):015008
[20]	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
[21]	Arioka K,Miyamoto T,Yamada T,et al.Role of cavity formation on crack growth of cold-worked carbon steel, TT 690 and MA 600 in high temperature water[A].Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors[C].Cham,2011:55
[22]	Arioka K,Yamada T,Miyamoto T,et al.Dependence of stress corrosion cracking of alloy 690 on temperature, cold work, and carbide precipitation—role of diffusion of vacancies at crack tips[J].Corrosion,2011,67:035006
[23]	Arioka K,Miyamoto T,Yamada T,et al.Role of cavity formation in crack initiation of cold-worked carbon steel in high-temperature water[J].Corrosion,2013,69:487
[24]	Wang S,Shoji T,Kawaguchi N.Initiation of environmentally assisted cracking in high-temperature water[J].Corrosion,2005,61:137
[25]	Arioka K,Iijima Y,Miyamoto T.Rapid nickel diffusion in cold-worked carbon steel at 320-450 ℃[J].Philos. Mag.,2015,95:3577
[26]	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
[27]	Andresen P L,Emigh P W,Young L M,et al.Stress corrosion crack growth rate behavior of Ni alloys 182 and 600 in high temperature water[A].Corrosion 2002[C].Denver,2002
[28]	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 Conference of Environmental Degradation of Materials in Materials in Nuclear Systems[C].Warrendale, PA,2003:834
[29]	Arioka K,Yamada T,Terachi T,et al.Influence of carbide precipitation and rolling direction on intergranular stress corrosion cracking of austenitic stainless steels in hydrogenated high-temperature water[J].Corrosion,2006,62:568
[30]	Moshier W C,Brown C M.Effect of cold work and processing orientation on stress corrosion cracking behavior of Alloy 600[J].Corrosion,2000,56:307
[31]	Gooch D J.The effect of anisotropy on creep and creep crack growth in cold-worked C-Mn steel at 360 ℃[J].Mater. Sci. Eng.,1987,91:45
[32]	Chen J J,Lu Z P,Xiao Q,et al.The effects of cold rolling orientation and water chemistry on stress corrosion cracking behavior of 316L stainless steel in simulated PWR water environments[J]. J. Nucl. Mater.,2016,472:1
[33]	Hou J,Peng Q J,Shoji T,et al.Effects of cold working path on strain concentration, grain boundary microstructure and stress corrosion cracking in Alloy 600[J].Corros. Sci.,2011,53:2956
[34]	Garc??a C,Mart??n F,De Tiedra P,et al.Effects of prior cold work and sensitization heat treatment on chloride stress corrosion cracking in type 304 stainless steels[J].Corros. Sci.,2001,43:1519
[35]	Lu W F,Lai C L,Huang J Y.Effects of hydrogen water chemistry on stress corrosion cracking behavior of cold-worked 304L stainless steel in high-temperature water environments[J].Mater. Trans.,2014,55:506
[36]	Meisnar M,Vilalta-Clemente A,Moody M,et al.A mechanistic study of the temperature dependence of the stress corrosion crack growth rate in SUS316 stainless steels exposed to PWR primary water[J].Acta Mater.,2016,114:15
[37]	Arioka K,Yamada T,Miyamoto T,et al.Intergranular stress corrosion cracking growth behavior of Ni-Cr-Fe alloys in pressurized water reactor primary water[J].Corrosion,2014,70:695
[38]	Shoji T.Progress in the mechanistic understanding of BWR SCC and its implication to the prediction of SCC growth behavior in plants[A].Proceedings of the 11th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors[C].Stevenson,2003:588
[39]	Fukai Y,ōkuma N.Evidence of copious vacancy formation in Ni and Pd under a high hydrogen pressure[J].Jpn. J. Appl. Phys.,1993,32:L1256
[40]	Fukai Y,ōkuma N.Formation of superabundant vacancies in Pd hydride under high hydrogen pressures[J].Phys. Rev. Lett.,1994,73:1640
[41]	Yamazaki Y,Iijima Y,Okada M.Enhanced diffusion of Au inγ-Fe by vacancies induced under elevated hydrogen pressure[J].Acta Mater.,2004,52:1247
[42]	Ford F P,Taylor D F,Andresen P L,et al.Environmentally-controlled cracking of stainless and low-alloy steels in lightwater reactor environments[R].NP-5064M, Final Report, EPRI,1987
[43]	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

[1]	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.
[2]	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.
[3]	ZHU Lixia, JIA Haidong, LUO Jinheng, LI Lifeng, JIN Jian, WU Gang, XU Congmin. Effect of Applied Potential on Stress Corrosion Behavior of X80 Pipeline Steel and Its Weld Joint in a Simulated Liquor of Soil at Lunnan Area of Xinjiang[J]. 中国腐蚀与防护学报, 2020, 40(4): 325-331.
[4]	ZHANG Zhen, WU Xinqiang, TAN Jibo. *Review of Electrochemical Noise Technique for in situ* Monitoring of Stress Corrosion Cracking**[J]. 中国腐蚀与防护学报, 2020, 40(3): 223-229.
[5]	CHEN Xu,MA Jiong,LI Xin,WU Ming,SONG Bo. Synergistic Effect of SRB and Temperature on Stress Corrosion Cracking of X70 Steel in an ArtificialSea Mud Solution[J]. 中国腐蚀与防护学报, 2019, 39(6): 477-483.
[6]	Baojie WANG,Jiyu LUAN,Shidong WANG,Daokui XU. Research Progress on Stress Corrosion Cracking Behavior of Magnesium Alloys[J]. 中国腐蚀与防护学报, 2019, 39(2): 89-95.
[7]	Ruolin ZHU, Litao ZHANG, Jianqiu WANG, Zhiming ZHANG, En-Hou HAN. Stress Corrosion Crack Propagation Behavior of Elbow Pipe of Nuclear Grade 316LN Stainless Steel in High Temperature High Pressure Water[J]. 中国腐蚀与防护学报, 2018, 38(1): 54-61.
[8]	Xiaocheng ZHOU, Qiaoqi CUI, Jinghuan JIA, Zhiyong LIU, Cuiwei DU. Influence of Cl^- Concentration on Stress Corrosion Cracking Behavior of 316L Stainless Steel in Alkaline NaCl/Na₂S Solution[J]. 中国腐蚀与防护学报, 2017, 37(6): 526-532.
[9]	Naiqiang ZHANG,Guoqiang YUE,Fabin LV,Qi CAO,Mengyuan LI,Hong XU. Crack Growth Rate of Stress Corrosion Cracking of Inconel 625 in High Temperature Steam[J]. 中国腐蚀与防护学报, 2017, 37(1): 9-15.
[10]	Jinheng LUO,Congmin XU,Dongping YANG. Stress Corrosion Cracking of X100 Pipeline Steel in Acid Soil Medium with SRB[J]. 中国腐蚀与防护学报, 2016, 36(4): 321-327.
[11]	Yueling GUO,En-Hou HAN,Jianqiu WANG. Effect of Post-forging Heat Treatment on Stress Corrosion Cracking of Nuclear Grade 316LN Stainless Steel in Boiling MgCl₂ Solution[J]. 中国腐蚀与防护学报, 2015, 35(6): 488-495.
[12]	Zhiming ZHANG,Qingjiao PENG,Jianqiu WANG,En-Hou HAN,Wei KE. Stress Corrosion Cracking Behavior of Forged 316L Stainless Steel Used for Nuclear Power Plants in Alkaline Solution at 330 ℃[J]. 中国腐蚀与防护学报, 2015, 35(3): 205-212.
[13]	SHI Xianbo, WANG Wei, YAN Wei, SHAN Yiyin, YANG Ke. Effect of Martensite/Austenite (M/A) Constituent on H₂S Resistance of High Strength Pipeline Steels[J]. 中国腐蚀与防护学报, 2015, 35(2): 129-136.
[14]	WANG Feng^,,WEI Chunyan,HUANG Tianjie^,,CUI Zhongyu,LI Xiaogang. Effect of H₂S Partial Pressure on Stress Corrosion Cracking Behavior of 13Cr Stainless Steel in Annulus Environment Around CO₂ Injection Well[J]. 中国腐蚀与防护学报, 2014, 34(1): 46-52.
[15]	MA Cheng,PENG Qunjia,HAN En-Hou,KE Wei. Review of Stress Corrosion Cracking of Structural Materials in Nuclear Power Plants[J]. 中国腐蚀与防护学报, 2014, 34(1): 37-45.

No Suggested Reading articles found!

Viewed

Full text

Abstract

Cited

Shared

Discussed