Effect of Pre-charged Hydrogen on the Oxide Film of 316L Stainless Steel in Simulated PWR Primary Water
摘 要
采用扫描电镜和X射线光电子能谱仪,分析了有无充氢冷加工316L不锈钢在300 ℃除氧的模拟压水堆一回路水中浸泡168 h后,其表面氧化膜的厚度及成分。结果表明:有无充氢试样表面形成的氧化膜均为双层结构,外层氧化膜的氧化物颗粒富含Fe,内层氧化膜的氧化物颗粒富含Cr。与未充氢试样比,充氢试样氧化膜的厚度较厚,外层氧化膜的氧化物颗粒较大且Fe与Cr的质量分数比较大;充氢导致试样内层氧化膜Fe含量升高,OH-与O2-的原子分数比增大,抑制了Cr氧化物的形成,使氧化膜中Cr含量下降,从而降低了氧化膜的保护性,加速基体的氧化。
Abstract
Through scanning electron microscopy and X-ray photoelectron spectroscopy, the thickness and composition of the oxide films formed on the surfaces of cold-worked 316L stainless steel with and without hydrogen-charging after immersion in deoxidized simulated PWR primary water at 300 ℃ for 168 h were analyzed. The results show that the oxide films of samples with and without hydrogen-charging were all double-layer structures. The oxide particles of the outer oxide film were rich in Fe, and the oxide particles of the inner oxide film were rich in Cr. The thickness of the hydrogen-charging sample oxide film increased, the oxide particles of the outer oxide film were larger and the ratio of Fe mass fraction to Cr mass fraction was greater, compared to the sample without hydrogen-charging. The hydrogen charging increased the Fe content of the inner oxide film of sample, increased the OH- and O2- atomic fraction ratio, inhibitted the formation of Cr oxide, and reduced the Cr content of oxide film, thereby reducing the protection of the oxide film and accelerating the oxidation of the substrate.
中图分类号 TG172 DOI 10.11973/fsyfh-202106001
所属栏目 试验研究
基金项目 国家科技重大专项(2015ZX06002005);国家自然科学基金(51771107)
收稿日期 2019/9/26
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引用该论文: CUI Tongming,CAI Shuangwei,NING Fei,ZHANG Kun,MA Jiarong,Lü Zhanpeng,WANG Donghui,ZHONG Zhimin. Effect of Pre-charged Hydrogen on the Oxide Film of 316L Stainless Steel in Simulated PWR Primary Water[J]. Corrosion & Protection, 2021, 42(6): 1
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【3】CHEN J J,XIAO Q,LU Z P,et al. Characterization of interfacial reactions and oxide films on 316L stainless steel in various simulated PWR primary water environments[J]. Journal of Nuclear Materials,2017,489:137-149.
【4】吕战鹏. 高温水中应力腐蚀开裂机理及扩展模型[J]. 中国材料进展,2019,38(7):651-662.
【5】BANDY R,ROOYEN D V. Stress corrosion cracking of inconel alloy 600 in high temperature water-an update[J]. Corrosion,1984,40(8):425-430.
【6】PENG H,XIAO Q,LI H,et al. The effect of hydrogen on the corrosion and anodic behavior of 13Cr stainless steel in chloride solution[J]. ECS Transactions,2016,72(17):41-50.
【7】QIAO L J,MAO X,CHU W Y. The role of hydrogen in stress-corrosion cracking of austenitic stainless steel in hot MgCl2 solution[J]. Metallurgical Materials Transactions A,1995,26A:1777-1784.
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【12】CUI T M,MA J R,ZHANG K,et al. Synergistic effect of solid state hydrogen and cold work pretreatment on oxide films grown on 316L stainless steel during short term immersion in deaerated high temperature water at 300℃[J]. Journal of the Electrochemical Society,2020,167:161502.
【13】WANG Z H,TAKEDA Y. Mechanistic understanding of the roles of hydrogen in modification of oxide film of alloy 600 in high temperature high pressure water environment[J]. Corrosion Science,2020,170:108656.
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【15】CHEN J J,LU Z P,MENG F J,et al. The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen[J]. Journal of Nuclear Materials,2019,517:179-191.
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【17】MACHET A,GALTAYRIES A,ZANNA S,et al. XPS and STM study of the growth and structure of passive films in high temperature water on a nickel-base alloy[J]. Electrochimica Acta,2004,49(22/23):3957-3964.
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【23】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.
【24】LOZANO-PEREZ S,YAMADA T,TERACHI T,et al. Multi-scale characterization of stress corrosion cracking of cold-worked stainless steels and the influence of Cr content[J]. Acta Materialia,2009,57(18):5361-5381.
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【29】YANG Z G,WALKER M S,SINGH P,et al. Oxidation behavior of ferritic stainless steels under SOFC interconnect exposure conditions[J]. Journal of the Electrochemical Society,2004,151(12):B669.
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