Effect of Surface Machining on the Corrosion Resistance of Oxide Film of Austenite Stainless Steel
摘 要
使用不同工艺参数对核电厂广泛使用的304L和316L奥氏体不锈钢进行表面铣削加工,然后在模拟压水堆核电站一回路水环境中进行浸泡氧化试验。对其表面形成的氧化膜进行点蚀和应力腐蚀性能评价。结果表明,虽然随着浸泡时间的延长,不锈钢表面氧化膜的耐蚀性有所增加,但铣削加工会显著降低两种不锈钢氧化膜的耐蚀性。随着浸泡时间的延长,表面形成的氧化膜不能减缓机加工后试样的应力腐蚀开裂,甚至部分氧化膜会因为脆化而加剧应力腐蚀开裂。
Abstract
Surface milling of 304L and 316L austenitic stainless steels with different processing parameters was carried out, and then immersion tests were conducted in simulated primary loop environmental water of pressurized water reactor nuclear power plants. The pitting corrosion and stress corrosion properties of the formed surface oxide film were evaluated. The results showed that milling could significantly reduce the corrosion resistance of the oxide films on the surface of two stainless steels, although the corrosion resistance of the oxide films increased with the prolongation of immersion test. Stress corrosion cracking of machined specimens could not be alleviated by the formation of oxide film on the surface with prolongation of immersion time, and even stress corrosion cracking of some oxide film was aggravated due to embrittlement.
中图分类号 TG174 DOI 10.11973/fsyfh-202009009
所属栏目 核电设备的腐蚀与防护
基金项目
收稿日期 2019/10/15
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引用该论文: WANG Wenjie,WANG Weihui,QI Bing. Effect of Surface Machining on the Corrosion Resistance of Oxide Film of Austenite Stainless Steel[J]. Corrosion & Protection, 2020, 41(9): 50
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参考文献
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【2】SUN H,WU X Q,HAN E H. Effects of temperature on the oxide film properties of 304 stainless steel in high temperature lithium borate buffer solution[J]. Corrosion Science,2009,51(12):2840-2847.
【3】KARLSEN W,DIEGO G,DEVRIENT B. Localized deformation as a key precursor to initiation of intergranular stress corrosion cracking of austenitic stainless steels employed in nuclear power plants[J]. Journal of Nuclear Materials,2010,406(1):138-151.
【4】LO K H,SHEK C H,LAI J K L. Recent developments in stainless steels[J]. Materials Science and Engineering:R:Reports,2009,65(4/5/6):39-104.
【5】WU H C,YANG B,WANG Y Q. Effect of sigma phase on the low cycle fatigue property of Z3CN20.09M cast duplex stainless steel in high temperature water[J]. Materials and Corrosion,2015,66(7):663-669.
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【8】WANG S Y,HU Y J,FANG K W,et al. Effect of surface machining on the corrosion behaviour of 316 austenitic stainless steel in simulated PWR water[J]. Corrosion Science,2017,126:104-120.
【9】HAN Y L,MEI J N,PENG Q J,et al. Effect of electropolishing on corrosion of nuclear grade 316L stainless steel in deaerated high temperature water[J]. Corrosion Science,2016,112:625-634.
【10】HAN Y L,HAN E H,PENG Q J,et al. Effects of electropolishing on corrosion and stress corrosion cracking of alloy 182 in high temperature water[J]. Corrosion Science,2017,121:1-10.
【11】CISSÉ S,LAFFONT L,TANGUY B,et al. Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water[J]. Corrosion Science,2012,56:209-216.
【12】郦晓慧,王俭秋,韩恩厚,等. 核级商用690合金和800合金在模拟压水堆核电站一回路高温高压水中的腐蚀行为研究[J]. 金属学报,2012,48(8):941-950.
【13】XU J,WU X Q,HAN E H. The evolution of electrochemical behaviour and oxide film properties of 304 stainless steel in high temperature aqueous environment[J]. Electrochimica Acta,2012,71:219-226.
【14】CHENG X Q,FENG Z C,LI C T,et al. Investigation of oxide film formation on 316L stainless steel in high-temperature aqueous environments[J]. Electrochimica Acta,2011,56(17):5860-5865.
【15】FÉRON D,HERMS E,TANGUY B. Behavior of stainless steels in pressurized water reactor primary circuits[J]. Journal of Nuclear Materials,2012,427(1/2/3):364-377.
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