Influence of Zn Addition on Oxide Films Formed on Alloy 690 in High Temperature Water

doi:10.11902/1005.4537.2013.196

Journal of Chinese Society for Corrosion and protection

2014, Vol. 34

Issue (6): 532-536 DOI: 10.11902/1005.4537.2013.196

Current Issue | Archive | Adv Search

Influence of Zn Addition on Oxide Films Formed on Alloy 690 in High Temperature Water

HAI Zhengyin¹(

), WANG Hui¹, XIN Changsheng¹, CAI Min¹, QIN Bo¹, CHEN Tong²

1. China Institute of Atomic Energy, Beijing 102413, China
2. Nuclear and Radiation Safety Center, Beijing 100082, China

Download:

HTML

PDF(2346KB)
Export: BibTeX | EndNote (RIS)

Abstract

The application of zinc injection at pressurized water reactors (PWRs) shows great benefits in reducing the radiation field and mitigating the primary water stress corrosion cracking (PWSCC) initiation and crack propagation of structure materials to a certain extent. The oxide film of Inconel 690 exposed to 300 ℃ dynamic high temperature water without/with 50 μg/kg Zn injection up to 1200 h has been investigated by XPS, SEM and EDS. It is revealed that the oxide film formed on Inconel 690 in the water with 50 μg/kg Zn addition is much thinner with grain size much smaller than that without Zn addition, while the distribution of grain size of the oxide film followed the Gauss function. The highest zinc concentration is found in the outer portion of the oxide layer close to the outer surface. Compounds ZnCr₂O₄and ZnFe₂O₄ with low Gibbs energy were formed on the surface of the alloy in water with Zn addition, which make the oxide film much more stable than those in the Zn free water.

Key words: Zn addition Alloy 690 high temperature water oxide film PWR

ZTFLH:

TG174.1

	Service

	E-mail this article
	Add to citation manager
	E-mail Alert
	RSS
	（）
	Articles by authors
	Zhengyin HAI
	Hui WANG
	Changsheng XIN
	Min CAI
	Bo QIN
	Tong CHEN

Cite this article:

HAI Zhengyin, WANG Hui, XIN Changsheng, CAI Min, QIN Bo, CHEN Tong. Influence of Zn Addition on Oxide Films Formed on Alloy 690 in High Temperature Water. Journal of Chinese Society for Corrosion and protection, 2014, 34(6): 532-536.

URL:

https://www.jcscp.org/EN/10.11902/1005.4537.2013.196 OR https://www.jcscp.org/EN/Y2014/V34/I6/532

Fig.1 SEM images of oxide films formed on Alloy 690 during exposure at 300 ℃ for 1200 h in dynamic high temperature deoxygenized water without Zn (a) and with 50 μg/kg Zn (b)

Fig.2 Grain size distributions of oxide film formed on Alloy 690 after exposure at 300 ℃ for 1200 h in dynamic high temperature deoxygenized water without Zn (a) and with 50 μg/kg Zn (b)

Fig.3 EDS spot analysis of oxide film of Alloy 690 exposed at 300 ℃ for 1200 h in dynamic high temperature deoxygenized water without Zn addition: (a) SEM image, (b) chemical composition of position 1, (c) chemical composition of position 2

Fig.4 EDS spot analysis of oxide film of Alloy 690 exposed at 300 ℃ for 1200 h in dynamic high temperature water with 50 μg/kg Zn addition: (a) SEM image, (b) chemical composition of position 1, (c) chemical composition of position

Fig.5 XPS element depth profile analysis of oxide film of Alloy 690 exposed at 300 ℃ for 1200 h in dynamic high temperature water without (a) and with (b) 50 μg/kg Zn addition

Fig.6 XPS Zn peak analysis of oxide films of Alloy 690 exposed at 300 ℃ for 1200 h in dynamic high temperature water with 50 μg/kg Zn addition after sputtering for 6 min (a) and 12 min (b)

Fig.7 GIXRD patterns of oxide films of Alloy 690 exposed at 300 ℃ for 1200 h in dynamic high temperature water without and with 50 μg/kg Zn addition

[1]	Chen H M,Ma C L,Bai X D. Corrosion and Protection of Nuclear Reactor Materials[M]. Beijin: Atomic Energy Press, 1984
	(陈鹤鸣,马春来,白新德. 核反应堆材料腐蚀及其防护[M]. 北京: 原子能出版社, 1984)
[2]	Marble W J, Wood C J. Control of BWR radiati on buildup with soluble zinc [A]. Corrosion/85 [C]. Boston: NACE, 1986: 107
[3]	Marble W J, Wood C J, Leighty C E, et al. BWR radiation buildup control with ionic zinc [A]. Proceedings of the 1986 Joint ASME/ANS Nuclear Power Conference [C]. Philadelphia: ANS, 1986: 144
[4]	Ziemniak S E, Hanson M. Corrosion behavior of 304 stainless steel in high temperature, hydrogenated water[J]. Corros. Sci., 2002, 44(10): 2209-2230
[5]	Ziemniak S E, Hanson M. Zinc Treatment effects on corrosion behavior of alloy 600 in high temperature, hydrogenated water[J]. Corros. Sci., 2006, 48: 3330-3348
[6]	Zhong W L, Li Z G, Wang W, et al. Evolution of high temperature and stress time effect on microstructure and properties of T91 steels[J]. Eng. J. Wuhan Univ., 2012, 45(1): 91-95
	(钟万里, 李正刚, 王伟等. 高温应力时效后T91钢组织与性能的演变[J]. 武汉大学学报 (工学版), 2012, 45(1): 91-95)
[7]	Huang J B, Liu X H, Han E-H, et al. Influence of Zn on oxide films on alloy 690 in borated and lithiated high temperature water[J]. Corros. Sci., 2011, 53: 3254-3261
[8]	Beverskog B. The role of zinc in LWRs [A]. Int. Conf. on Water Chemistry of Nuclear Reactor Systems [C]. San Francisco: IFE, 2004: 26
[9]	Jiang S Q. Tthe effects of zinc injection on corrosion behaviors of PWR primary loop structural materials [D]. 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]. 上海交通大学, 2011)

[1]	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.
[2]	XIAO Jintao,CHEN Yan,XING Mingxiu,JU Pengfei,MENG Yingen,WANG Fang. Effect of Process Parameters on Corrosion Resistance of Anodizing Film on 2195 Al-Li Alloy[J]. 中国腐蚀与防护学报, 2019, 39(5): 431-438.
[3]	Li FENG, Ligong ZHANG, Sizhen LI, Dajiang ZHENG, Changjian LIN, Shigang DONG. Effect of Ferric Citrate on Microstructure and Corrosion Resistance of Micro-arc Oxidation Black Film on Mg-alloy AZ40M[J]. 中国腐蚀与防护学报, 2017, 37(4): 360-365.
[4]	Jiamei WANG,Hui LU,Zhengang DUAN,Lefu ZHANG,Fanjiang MENG,Xuelian XU. Effect of Temperature on Electrochemical Behavior of Alloy 690 in Simulated PWR Secondary Circuit Water[J]. 中国腐蚀与防护学报, 2016, 36(2): 113-120.
[5]	Xiaoqiang LIU,Xuelian XU,Jibo TAN,Yuan WANG,Xinqiang WU,Yuli ZHENG,Fanjiang MENG,En-Hou HAN. Effect of Reactor Coolant Environment on Fatigue Performance of Alloy 690 Steam Generator Tubes[J]. 中国腐蚀与防护学报, 2015, 35(3): 213-219.
[6]	SHEN Zhao, ZHANG Lefu, ZHU Fawen, BAO Yichen. Corrosion Behavior of Candidate SCWR Fuel Cladding Materials[J]. 中国腐蚀与防护学报, 2014, 34(4): 301-306.
[7]	DUAN Zhengang, ZHANG Lefu, WANG Li, XU Xuelian, SHI Xiuqiang. Effect of Zn Addition on Composition of Oxide Scales Formed on 316L Stainless Steel in High-temperature and High-pressured Water[J]. 中国腐蚀与防护学报, 2014, 34(3): 249-252.
[8]	HAI Zhengyin, WANG Hui, CAO Linyuan, HU Yong. Effect of Pt Deposit on Corrosion Behavior of 316LN in Simulated Primary Loop Water Environment of Pressurized Water Reactor[J]. 中国腐蚀与防护学报, 2014, 34(3): 253-256.
[9]	DUAN Zhengang, ZHANG Lefu, JIANG Suqing, SHI Xiuqiang, XU Xuelian. Effect of Zn Addition on Behavior of Deposited Co in Oxide Scales of Alloys in PWR Primary Water[J]. 中国腐蚀与防护学报, 2014, 34(2): 192-194.
[10]	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.
[11]	TAN Yu,LIANG Kexin,ZHANG Shenghan. Photo-electrochemical Study on Semiconductor Properties of Oxide Films Formed on 316L Stainless Steel in High Temperature Water[J]. 中国腐蚀与防护学报, 2013, 33(6): 491-495.
[12]	MENG Fanjiang,WANG Jianqiu,HAN En-Hou,KE Wei. Stress Corrosion Crack Initiation for Scratched Alloy 690TT in Oxygenated High Temperature Water[J]. 中国腐蚀与防护学报, 2013, 33(5): 413-418.
[13]	YANG Zhongbo,ZHAO Wenjin,MIAO Zhi. Effect of Sn Content on Corrosion Resistance of N36 Alloys in LiOH Aqueous Solution[J]. 中国腐蚀与防护学报, 2013, 33(2): 117-122.
[14]	SUN Rongpeng,WANG Jianqiu,Han En-Hou. Effects of ETA Concentration on Corrosion of Carbon Steel and Nickel Based Alloy 690 in Nuclear Power Plant on Secondary Side[J]. 中国腐蚀与防护学报, 2013, 33(2): 97-103.
[15]	FENG Wanli, ZHANG Lefu, MA Mingjuan. EFFECTS OF ROLLING ON THE SPECIAL GRAIN BOUNDARIES AND INTERGRANULAR CORROSION OF ALLOY 690[J]. 中国腐蚀与防护学报, 2012, 32(4): 296-299.

No Suggested Reading articles found!

Viewed

Full text

Abstract

Cited

Shared

Discussed