STRESS CORROSION CRACK PROPAGATION BEHAVIOR OF DOMESTIC FORGED NUCLEAR GRADE 316L STAINLESS STEEL IN HIGH TEMPERATURE AND HIGH PRESSURE WATER

doi:10.3724/SP.J.1037.2013.00171

Acta Metall Sin

2013, Vol. 49

Issue (8): 911-916 DOI: 10.3724/SP.J.1037.2013.00171

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STRESS CORROSION CRACK PROPAGATION BEHAVIOR OF DOMESTIC FORGED NUCLEAR GRADE 316L STAINLESS STEEL IN HIGH TEMPERATURE AND HIGH PRESSURE WATER

ZHANG Litao,WANG Jianqiu

State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences,Shenyang 110016

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ZHANG Litao,WANG Jianqiu. STRESS CORROSION CRACK PROPAGATION BEHAVIOR OF DOMESTIC FORGED NUCLEAR GRADE 316L STAINLESS STEEL IN HIGH TEMPERATURE AND HIGH PRESSURE WATER. Acta Metall Sin, 2013, 49(8): 911-916.

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Abstract

Stress corrosion cracking growth rates of domestic forged nuclear grade 316L stainless steel (SS) were successfully measured in high temperature and high pressure water at various temperatures and under various loading mode. A direct current potential drop (DCPD) technique was used to monitor the crack growth throughout the test. The crack growth rate decreases with the increasing dissolved hydrogen content and the decreasing dissolved oxygen content. The crack growth rate under trapezoidal loading mode is bigger than that under constant loading. The fracture surface has typical intergranular stress corrosion cracking (IGSCC) characteristics.

Key words: direct current potential drop (DCPD) domestic forged nuclear grade 316L stainless steel high temperature and high pressure water stress corrosion crack growth rate

Received: 08 April 2013

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https://www.ams.org.cn/EN/10.3724/SP.J.1037.2013.00171 OR https://www.ams.org.cn/EN/Y2013/V49/I8/911

[1] Han E H. Acta Metall Sin, 2011; 47: 769
(韩恩厚. 金属学报, 2011; 47: 769)
[2] Han E H, Wang J Q, Wu X Q, Ke W. Acta Metall Sin, 2010; 46: 1379
(韩恩厚, 王俭秋, 吴欣强, 柯伟. 金属学报, 2010; 46: 1379)
[3] Lu Z P, Shoji T, Takeda Y, Ito Y, Kai A, Tsuchiya N. Corros Sci, 2008; 50: 625
[4] Meng F J, Lu Z P, Shoji T, Wang J Q, Han E H, Ke W. Corros Sci, 2011; 53: 2558
[5] Lu Z P, Shoji T, Takeda Y, Ito Y, Yamazaki S. Corros Sci, 2008; 50: 698
[6] Xue H, Li Z J, Lu Z P, Shoji T. Corros Sci, 2011; 241: 731
[7] Andresen P L, Briant C L. Corrosion, 1989; 45: 448
[8] Andresen P L. Corrosion, 1991; 47: 917
[9] Andresen P L. Corrosion, 1993; 49: 714
[10] Andresen P L. Corrosion, 1987; 44: 450
[11] Andresen P L, Kim Y J. Corrosion, 2003; 59: 584
[12] Bali S C, Kain V, Raja V S. Corrosion, 2009; 65: 726
[13] Peng Q J, Teysseyre S, Andresen P L, Was G S. Corrosion, 2007; 63: 1033
[14] Arioka K, Yamada T, Terachi T, Chiba G. Corrosion, 2007; 63: 1114
[15] Arioka K, Yamada T, Terachi T, Chiba G. Corrosion, 2006; 62: 568
[16] Byun T S, Hashimoto N, Farrell K. Acta Mater, 2004; 52: 889
[17] Yamazaki S, Lu Z P, Ito Y, Takeda Y, Shoji T. Corros Sci, 2008; 50: 835
[18] Lu Z P, Shoji T, Takeda Y, Ito Y, Yamazaki S. Corrosion, 2007; 63: 1021
[19] Andresen P L, Morra M M. J Nucl Mater, 2008; 383: 97
[20] Peng Q J, Hou J, Sakaguchi K, Takeda Y, Shoji T. Electrochim Acta, 2011; 56: 8375
[21] Andresen P L. Corrosion, 2008; 64: 439
[22] Andresen P L, Hickling J, Ahluwalia A, Wilson J. Corrosion, 2008; 64: 707
[23] Andresen P L, Briant C L. Corrosion, 1989; 45: 448
[24] Andresen P L. Corrosion, 1988; 44: 450
[25] Lu Z P, Shoji T, Takeda Y, Ito Y, Akira K, Tsuchiya N. Corros Sci, 2008; 50: 625

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