Fe、Cr过饱和固溶量对Zr-4合金耐蚀性的影响
Effects of Fe and Cr Supersaturated Solid Solution Contents on Corrosion Resistance of Zr-4 Alloy
摘 要
制备了4种Fe、Cr过饱和固溶量不同的Zr-4合金试样，采用透射电镜分析了4种试样的显微组织，并研究了4种试样在500℃/10.3 MPa和360℃/18.6 MPa/0.01 mol/L LiOH水溶液中的腐蚀规律。结果表明：在Zr-4合金未发生疖状腐蚀的情况下，降低α-Zr中过饱和固溶的Fe、Cr含量有利于改善Zr-4合金在500℃/10.3 MPa蒸汽中的耐均匀腐蚀性能。提高α-Zr中过饱和固溶的Fe、Cr含量有利于改善Zr-4合金在LiOH水溶液中的耐均匀腐蚀性能。
Fe、Cr过饱和固溶量
显微组织
耐蚀性
Zr-4 alloy
Fe and Cr supersaturation solid solution contents
microstructure
corrosion resistance
Abstract
Zr-4 alloy samples with different Fe and Cr supersaturation solid solution contents were prepared. Microstructure of samples was analyzed by transmission electron microscopy, and the corrosion law of those 4 samples was studied in 500℃/10.3 MPa steam and 360℃/18.6 MPa/0.01 mol/L LiOH solution. The results show that in the case of absence for Zr-4 alloy nodular corrosion, reducing the supersaturated solid solution content of Fe, Cr in α-Zr can improve uniform corrosion of Zr-4 alloy in 500℃/10.3 MPa steam. The corrosion resistance of Zr-4 alloy in LiOH solution can be improved by increasing the content of Fe and Cr in supersaturated solid solution in α-Zr.
中图分类号 TG174 DOI 10.11973/fsyfh-201707005
所属栏目 核电设备材料防护
基金项目 国家核电技术公司员工自主创新项目专项资金（SNP-KJ-CX-2014-11）
收稿日期 2016/10/30
修改稿日期
网络出版日期
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引用该论文: SUN Guocheng,TONG Longgang,GAO Bo,WU Nan. Effects of Fe and Cr Supersaturated Solid Solution Contents on Corrosion Resistance of Zr-4 Alloy[J]. Corrosion & Protection, 2017, 38(7): 507
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参考文献
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【3】GODLEWSKI J,GROS J P,LARNBERTIN M,et al. Raman spectroscopy study of the tetragonal-to-monoclinic transition in zirconium oxide scales and determination of overall oxygen diffusion by nuclear microanalysis of O[C]//Zirconium in the Nuclear Industry:9th International Symposium.[S.l.]:ASTM International,1991:416-436.
【4】BARBERIS P. Zirconia powders and zircaloy oxide films:tetragonal phase evolution during 400℃ autoclave tests[J]. Journal of Nuclear Materials,1995,226:34-43.
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【6】姚美意,周邦新,李强,等. 热处理对Zr-4合金在360℃ LiOH水溶液中腐蚀行为的影响[J]. 稀有金属材料与工程,2007,36(11):1920-1923.
【7】周邦新,姚美意,李强,等. Zr-4合金薄板的织构与耐疖状腐蚀性能的关系[J]. 上海大学学报(自然科学版),2008,14(5):441-445.
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【9】GARZAROLLI F,STEINBERG E,WEIDINGER H G. Microstructure and corrosion studies for optimized PWR and BWR zircaloy cladding[C]//Zirconium in the Nuclear Industry:8th International Symposium.[S.l.]:ASTM International,1989:202-212.
【10】HUTCHINSON B, LEHTINEN B,LIMBÄCK M,et al. A study of the structure and chemistry in zircaloy-2 and the resulting oxide after high temperature corrosion[C]//Zirconium in the Nuclear Industry:15th International Symposium.[S.l.]:ASTM International,2008:269-280.
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