国产锻造态核级管材<span>316L不锈钢在高温高压水中的应力腐蚀裂纹扩展行为</span>

doi:10.3724/SP.J.1037.2013.00171

金属学报

2013, Vol. 49

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

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国产锻造态核级管材316L不锈钢在高温高压水中的应力腐蚀裂纹扩展行为

张利涛,王俭秋

中国科学院金属研究所金属腐蚀与防护国家重点实验室, 沈阳 110016

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

引用本文:

张利涛,王俭秋. 国产锻造态核级管材316L不锈钢在高温高压水中的应力腐蚀裂纹扩展行为[J]. 金属学报, 2013, 49(8): 911-916.
ZHANG Litao, WANG Jianqiu. STRESS CORROSION CRACK PROPAGATION BEHAVIOR OF DOMESTIC FORGED NUCLEAR GRADE 316L STAINLESS STEEL IN HIGH TEMPERATURE AND HIGH PRESSURE WATER[J]. Acta Metall Sin, 2013, 49(8): 911-916.

全文: PDF(800 KB)

摘要:

采用直流电位降(DCPD)方法, 实现了模拟核电站高温高压水环境中的国产锻造态核级管材316L不锈钢应力腐蚀裂纹扩展速率的实时检测.断口观察表明, 国产316L不锈钢在高温高压水环境中表现出明显的沿晶应力腐蚀开裂(IGSCC)行为.降低溶解O含量, 增加溶解H含量能够显著降低应力腐蚀裂纹扩展速率;梯形波载荷下的裂纹扩展速率大于恒载荷下的扩展速率, 裂纹扩展速率随着(t_fl=t_rs)/t_h比值的增加而升高.

关键词 ：直流电位降, 国产锻造态核级管材316L不锈钢, 高温高压水, 应力腐蚀裂纹扩展速率

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

收稿日期: 2013-04-08

基金资助:

国家科技重大专项课题项目2011ZX06004--002和国家自然科学基金项目51025104资助

作者简介: 张利涛, 男, 1988年生, 博士生

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https://www.ams.org.cn/CN/10.3724/SP.J.1037.2013.00171 或 https://www.ams.org.cn/CN/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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