热老化316L不锈钢在模拟核电溶解氧/氢高温高压水中应力腐蚀裂纹扩展行为

doi:10.11896/cldb.19030167

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Abstract The crack growth rate (CGR) of stress corrosion cracking (SCC) of thermally aged 316L stainless steel (SS) for 2 000 h in simulated primary high temperature and high pressure water of 1.5×10^-3 B and 2.3×10^-6 Li at 320 ℃ and 13 MPa is tested using direct current potential drop (DCPD) system and high temperature and high pressure corrosion test system. Results show the CGR of thermally aged 316L SS is decreased gradually with the dissolved oxygen (DO) content in the solution decreasing from 2×10^-6 to 10^-6, 5×10^-7, 10^-7 and 5×10^-9. When the DO content decreasing from 5×10^-7 to the lower, the CGR of SCC is decreased significantly. The CGR is further decreased, when the solution is changed from DO to dissolved hydrogen (DH). Scanning electron microscopy (SEM) and electron back scattering diffraction (EBSD) are used to observe the fractures and crack propagation paths of the tested specimens. SCC fracture mainly presents a typical characteristic of intergranular stress corrosion cracking (IGSCC). The change of DO/DH mainly affects the mass transfer process of cracks tip and the repassivation process of the bare surface at cracks tip, which further affects the CGR. The thermal aging of 316L SS for 2 000 h has a small effect on its microstructure and CGR of SCC in high temperature and high pressure water.

Key words： dissolved oxygen/hydrogen thermal aging stainless steel high temperature and high pressure water stress corrosion cracking crack growth rate

Published: 12 March 2020

CLC number:

TG172.82

Fund:This work was financially supported by National Key Research and Development Program (2017YFB0702100), National Natural Science Foundation (51771211), Key Research Program of Frontier Sciences, Chinese Academy of Sciences (QYZDY-SSW-JSC012), Key Program of the Chinese Academy of Sciences (ZDRW-CN-2017-1).

About author:: Wenbo Wugraduated from School of Materials Science and Engineering, Xiangtan University. He is currently pursuing his Master's degree at School of Materials Scie-nce and Engineering, University of Science and Technology of China. His research has focused on study of stress corrosion cracking initiation and propagation behavior of nuclear key metal materials; Zhiming Zhangreceived his Ph.D. degree in corrosion science and protection from Graduate University of Chinese Academy of Sciences in 2012. His is currently an associate professor at Institute of Metal Research, Chinese Academy of Sciences. His main research inte-rests include environmentally service behavior and safety assessment of key metal materials used in nuclear related facilities. In recent 5 years, he has more than 30 scientific papers published.

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Cite this article:

WU Wenbo,ZHANG Zhiming,WANG Jianqiu, et al. Stress Corrosion Cracking Behavior of Thermally Aged 316L SS in Simulated Oxygenated/Hydrogenated High Temperature and Pressure Water in Nuclear Power Plants[J]. Materials Reports, 2020, 34(6): 6144-6150.

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http://www.mater-rep.com/EN/10.11896/cldb.19030167 OR http://www.mater-rep.com/EN/Y2020/V34/I6/6144

1 Andresen P L. Corrosion, 2013, 69 (10),1024.
2 Andresen P L, Morra M M. Corrosion, 2008, 64 (1),15.
3 Qiu X P, Tan J. Nuclear Electronics & Detection Technology, 2005 (1),84 (in Chinese).
邱小平,谭健.核电子学与探测技术,2005 (1),84.
4 Spruiell J E, Scott J A, Ary C S, Metallurgical and Materials Transactions B, 1973, 4 (6),1533.
5 Li Y F. Study of stress corrosion cracking susceptibility of nickel-based welds in safe-end dissimilar metal weld in pressurized water reactor. Ph.D. Thesis, University of Science and Technology of China,China,2018 (in Chinese).
李毅丰.压水堆安全端异种金属焊接接头镍基焊缝材料应力腐蚀开裂敏感性研究.博士学位论文,中国科学技术大学,2018.
6 Stoter L P. Journal of Materials Science, 1981, 16 (4),1039.
7 Keown S R, Thomas R G. Metal Science, 1981, 15 (9),386.
8 O′Donnell I J, Huthmann H, Tavassoli A A. International Journal of Pressure Vessels & Piping, 1996, 65 (3),209.
9 Wang M, Chen L, Liu X, et al.Corrosion Science, 2014, 81 (4),117.
10 Li S L, Li S X, Wang Y L, et al. Acta Metallurgica Sinica, 2010,46 (10),1186 (in Chinese).
李时磊,李树肖,王艳丽,等.金属学报,2010,46 (10),1186.
11 Zhang Y. The investigation on thermal aging and stress corrosion cracking sensibility of the forged 316LN austenitic stainless steel. Master's Thesis, Yanshan University, China, 2012 (in Chinese).
张勇.锻造316LN材料热老化与应力腐蚀开裂敏感性研究.硕士学位论文,燕山大学, 2012.
12 Xu W J, Bai X D. The thermal aging and life prolonged of nuclear materials, Chemical Industry Press, China,2015 (in Chinese).
许维钧,白新德. 核电材料老化与延寿,化学工业出版社,2015.
13 Chung H M, Ruther W E, Sanecki J E, et al. Journal of Nuclear Mate-rials, 1996,239 (1-3),61.
14 Jenssen A, Ljungberg L G, Walmsley J, et al. Corrosion, 1998,54 (1),48.
15 Andresen P, Catlin W, Morra M. In: Proceedings of NACE Corrosion 2004. New Orleans, Louisiana,2004,pp.04678.
16 Li G F, Kaneshima Y, Shoji T. Corrosion, 2000,56 (5),460.
17 Lu Z, Shoji T, Takeda Y, et al. Corrosion, 2007,63 (11),1021.
18 Lu Z, Shoji T, Meng F, et al. Corrosion Science, 2011,53 (1),247.
19 Saito N, Kikuchi E, Sakamoto H, et al. Corrosion, 1997,53 (7),537.
20 Kikuchi E, Itow M, Kuniya J, et al. Corrosion, 1997,53 (4),306.
21 Zhang L T. Stress corrosion crack growth behavior of nuclear grade 316L stainless steel in pressurized temperature water. Ph.D. Thesis, University of Chinese Academy of Science, China, 2014 (in Chinese).
张利涛. 核级316L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.博士学位论文,中国科学院大学,2014.
22 Bai X D. Nuclear material chemistry, 1^st edition, Chemical Industry Press, China, 2007 (in Chinese).
白新德. 核材料化学, 第一版, 化学工业出版社, 2007.
23 Mailand I, Venz H. In:An Approved Method To Reduce Dose Rate: International Conference on Water Chemistry of Nuclear Reactor Systems, Berlin, 2008.
24 Kuang W, Wu X, Han E. Corrosion Science, 2013,69,197.
25 Chung H M, Leax T R. Metal Science Journal, 1989, 6 (3),249.
26 Auger P, Danoix F, Menand A, et al. Metal Science Journal, 2013, 6 (3),301.
27 Chung H M. International Journal of Pressure Vessels & Piping, 1992, 50 (1-3),179.
28 Pumphrey P H, Akhurst K N. Materials Science and Technology,1990, 6, 211.
29 ASTM-E647-11, American Society of Testing Materials, America,2011.
30 中华人民共和国国家质量监督检疫总局,中国国家标准化管理委员会.《金属和合金的腐蚀双环电化学动电位再活化测量法》. GB/T29088,2012.
31 Davis J R. Metals handbook, 9^th edition, China Machine Press, China, 2011 (in Chinese).
戴维斯.金属手册, 第九版,机械工业出版社,2011.
32 Peckener D,Bernstein I M. Handbook of stainless steels, McGraw-Hill Company,USA,1997.
33 Lewis A C, Bingert J F, Rowenhorst D J, et al. Materials Science and Engineering: A, 2006, 418 (1-2),11.
34 Wang C L. Phase diagrams and its application,Higher Education Press,China,2014 (in Chinese).
王崇琳. 相图理论及其应用, 高等教育出版社, 2014.
35 Dutt B S, Babu M N, Shanthi G, et al. Journal of Materials Engineering and Performance,2018,4,1957.
36 Seifert H P, Ritter S, Leber H J,et al.Corrosion Science, 2012, 59 (2),20.
37 Sadananda K,Vasudevan A K.International Journal of Fatigue,1999,16 (6),1.
38 Zhang L T, Wang J Q. Acta Metallurgica Sinica, 2013,49 (8),911 (in Chinese).
张利涛,王俭秋.金属学报,2013,49 (8),911.
39 Zhu R, Wang J, Zhang L, et al. Corrosion Science,2016,112,373.
40 Terachi T, Fujii K, Arioka K. Journal of Nuclear Science and Technology, 2005,42 (2),225.
41 Ford F P. Corrosion, 1996,52 (5),375.
42 Andresen P L.In:Critical Processes to Model in Predicting SCC Response in Hot Water. Corrosion, Houston,NACE,2005,pp.05470.
43 Cao C N, Principles of corrosion electrochemistry, Chemical Industry Press, China, 2004 (in Chinese).
曹楚南. 腐蚀电化学原理, 化学工业出版社,2004.
44 Jang H, Cho P, Jang C, et al. Transactions of the Korean Society of Mechanical Engineers A, 2014, 38 (1),11.
45 Andresen P.Corrosion,2008,64 (5),439.
46 Arioka K, Yamada T, Terachi T, et al. Corrosion, 2007, 63 (12),1114.
47 Du D, Kai C, Hui L, et al. Corrosion Science, 2016, 110,134.
48 Du D, Chen K, Yu L, et al. Journal of Nuclear Materials, 2015, 456,228.