期刊文献+

Zr-Sn-Nb-Fe-Mo合金在高温高压水中的腐蚀行为

Corrosion Behaviors of Zr-Sn-Nb-Fe-Mo Alloy in High Temperature and High Pressure Water
下载PDF
导出
摘要 采用高压釜腐蚀试验研究了Zr-Sn-Nb-Fe-Mo合金在360℃/18.6 MPa去离子水中的耐蚀性,采用扫描电子显微镜(SEM)、透射电子显微镜(TEM)和激光拉曼光谱分析了合金腐蚀前后的显微组织。结果表明:合金在腐蚀300d的腐蚀增重相比ZIRLO合金的降低了30%以上。合金中生成了均匀弥散的HCP结构的Zr(Nb,Fe)2和Zr(Nb,Fe,Mo)2第二相颗粒。腐蚀260d后氧化膜中出现明显的平行于氧化膜/基体界面的裂纹,四方相t-ZrO2含量显著减少是氧化膜中产生裂纹并加速合金腐蚀的重要因素。添加Mo元素生成的Zr(Nb,Fe,Mo)2第二相颗粒起到了延迟氧化并减小氧化膜内应力的作用。 The corrosion resistance of Zr-Sn-Nb-Fe-Mo alloy in 360℃/18.6 MPa deionized water was studied by autoclave corrosion test.Scanning electron microscopy(SEM),transmission electron microscopy(TEM)and laser Raman spectroscopy were used to analyze the microstructure of the alloy before and after corrosion.The results showed that the corrosion weight gain of the alloy after 300 days of corrosion reduced by more than 30%compared to ZIRLO alloy.Zr(Nb,Fe)2 and Zr(Nb,Fe,Mo)2 second phase particles with HCP structure generated in the alloy were dispersed uniformly.After 260 days of corrosion,there were obvious cracks in the oxide film parallel to the oxide film/substrate interface.The significant reduction of t-ZrO2 in the tetragonal phase was an important factor that caused cracks in the oxide film and accelerated alloy corrosion.The Zr(Nb,Fe,Mo)2 second-phase particles generated by adding Mo element played a role in delaying oxidation and reducing the internal stress in the oxide film.
作者 卢俊强 陈芙梁 曾奇锋 石慧岗 郭相龙 LU Junqiang;CHEN Fuliang;ZENG Qifeng;SHI Huigang;GUO Xianglong(Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.,Shanghai 200233,China;Shanghai Jiao Tong University,Shanghai 200240,China)
出处 《腐蚀与防护》 CAS 北大核心 2020年第9期32-38,共7页 Corrosion & Protection
基金 大型先进压水堆核电站重大专项(2019ZX06002001)。
关键词 锆合金 腐蚀性能 第二相颗粒 氧化膜 zirconium alloy corrosion resistance second phase particle oxide film
  • 相关文献

参考文献3

二级参考文献23

  • 1周邦新,李聪,黄德诚.Zr(Fe,Cr)_2金属间化合物的氧化[J].核动力工程,1993,14(2):149-153. 被引量:14
  • 2周邦新.锆合金中的疖状腐蚀问题[J].核科学与工程,1993,13(1):51-58. 被引量:27
  • 3周邦新,李强,姚美意,刘文庆,褚玉良.锆-4合金在高压釜中腐蚀时氧化膜显微组织的演化[J].核动力工程,2005,26(4):364-371. 被引量:46
  • 4周邦新,李强,刘文庆,姚美意,褚于良.水化学及合金成分对锆合金腐蚀时氧化膜显微组织演化的影响[J].稀有金属材料与工程,2006,35(7):1009-1016. 被引量:42
  • 5Zhou B X,Li Q, Yao M Y, et al. Effect of water chemistry and composition on microstructural evolution of oxide on Zr-Alloys, zirconium in the nuclear industry: 15^th International Symposium[EB/OL]. Sunriver Oregon US, 2007, June, 24- 28. (paper ID JAI 10112, available online at www. astrn, org).
  • 6Yilmazbayhan A, Motta A T, Comstock R J, et al. Structure of zirconium alloy oxides formed in prre water studied with synchrotron radiation and optical microscopy:relation to corrosion rate[J]. J Nuel Mater [J]. 2004,324:6-22.
  • 7Yilmazbayhan A, Breval E, Motta A T, et al. Transmission electron microscopy examination of oxide layer formed on Zr alloys[J]. J Nucl Mater, 2006,349:265 -281.
  • 8Bryner J S. The cyclic nature of corrosion of Zircaloy-4 in 633K water[J]. J Nucl Mater. , 1979,82:84-88.
  • 9Comstock R J, Schoenberger G, Sabol G P. Influence of processing variables and alloy chemistry on the corrosion behavior of ZIRLO nuclear fuel cladding, Zirconium in the nuclear industry. Eleventh International Symposium[C]//ASTM STP 1295, Bradley E R and Sabol G P, Eds. American Society for Testing and Materials, 1996 : 710-725.
  • 10Cox B. Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys[J]. J Nucl Mater, 2005,336 : 331-368.

共引文献33

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部