期刊文献+

Pd添加对Zr-4合金在LiOH水溶液中耐腐蚀性能的影响 被引量:4

Effect of Pd addition on corrosion resistance of Zr-4 alloy in LiOH solution
下载PDF
导出
摘要 采用静态高压釜腐蚀实验研究添加微量Pd元素的Zr-4合金在(360℃,18.6 MPa)条件下0.01 mol/L Li OH水溶液中的耐腐蚀性能,采用TEM和SEM研究合金和氧化膜的显微组织。结果表明:添加0.05%~0.2%Pd(质量分数)均可明显改善Zr-4合金在Li OH水溶液中的耐腐蚀性能,其中添加0.1%Pd时改善作用最显著,随着添加Pd含量的进一步增加,对Zr-4合金耐腐蚀性能的改善作用减弱。在Zr-4合金中Pd元素以Zr2(Fe,Cr,Pd)、Zr2(Pd,Fe)形式的第二相析出,其中Zr2(Pd,Fe)第二相尺寸较大。固溶在α-Zr中的Pd和尺寸较小的Zr2(Fe,Cr,Pd)型第二相可以提高Zr-4合金的耐腐蚀性能;析出尺寸较大的Zr2(Pd,Fe)第二相后会对Zr-4合金的耐腐蚀性能产生不利的影响。 The corrosion resistance of Zr-4 alloy with Pd addition in 0.01 mol/L LiOH solution at 360 ℃ and 18.6 MPa was studied by autoclave test. The microstructures of the alloys and oxide layers were investigated by TEM and SEM. The results show that the corrosion resistance of Zr-4 alloy in LiOH solution is markedly improved with the addition of 0.05%-0.2% Pd. And the Zr-4 alloy with the addition of 0.1%Pd shows the best corrosion resistance. The role of improving the corrosion resistance of Zr-4 alloy weakens when the Pd content further increases. The alloying element of Pd is precipitated as the second phase particles(SPPs) of Zr2(Fe,Cr,Pd) and Zr2(Pd,Fe) in Zr-4 alloys. The SPPs of Zr2(Pd,Fe) are comparably coarse. The solid solution of Pd in α-Zr matrix and the precipitates of fine SPPs of Zr2(Fe,Cr,Pd) are beneficial to improve the corrosion resistance of Zr-4 alloy, while the coarse SPPs of Zr2(Pd,Fe) are harmful to the corrosion resistance.
出处 《中国有色金属学报》 EI CAS CSCD 北大核心 2015年第3期675-681,共7页 The Chinese Journal of Nonferrous Metals
基金 国家自然科学基金资助项目(51171102)
关键词 锆合金 ZR-4合金 耐腐蚀性能 氧化膜 zirconium alloy Zr-4 alloy corrosion resistance oxide film
  • 相关文献

参考文献18

  • 1C. Proff,S. Abolhassani,C. Lemaignan.Oxidation behaviour of zirconium alloys and their precipitates – A mechanistic study[J]. Journal of Nuclear Materials . 2013 (1-3)
  • 2Cox, B.,Yamaguchi, Y.Development of porosity in thick zirconia films. Journal of Nuclear Materials . 1994
  • 3Foster, John P.,Dougherty, J.,Burke, M.G.,Bates, J.F.,Worcester, S.Influence of final recrystallization heat treatment on Zircaloy-4 strip corrosion. Journal of Nuclear Materials . 1990
  • 4GARZAROLLI F,BROY Y,BUSCH R A.Comparison of the long-time corrosion behavior of certain Zr alloys in PWR,BWR,and laboratory. . 1996
  • 5ANADA H,HERB B J,NOMOTO K,HAGI S,GRAHAM R A,KURODA T.Effect of annealing temperature on corrosion behavior and Zr O2 microstructure of Zircaloy-4 cladding tube. . 1996
  • 6SABOL G P,COMSTOCK R J,WEINER R A,LAROUERE E,STANUTZ R N.In-reactor corrosion performance of ZIRLO and Zircaloy-4. . 1994
  • 7NIKULINA A V,MARKELOV V A,PEREGUD M M.Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK cores. . 1996
  • 8ZHOU Bang-xin,LI Qiang,YAO Mei-yi,LIU Wen-qing,CHU Yu-liang.Effect of water chemistry and composition on microstructural evolution of oxide on Zr alloys. . 2008
  • 9BROY Y,GARZAROLLI F,SEIBOLD A,VAN-SWAM L E.Twelfth International Symposium on Zirconium in the Nuclear Industry. . 2000
  • 10张欣,姚美意,李中奎,周军,李强,周邦新.Zr-0.80Sn-0.4Nb-0.4Fe-0.10Cr-xCu合金在400℃过热蒸气中的耐腐蚀性能[J].稀有金属材料与工程,2013,42(6):1210-1214. 被引量:15

二级参考文献96

  • 1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
  • 2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:43
  • 3Cox B, Wong Y M. In: Eucken C M, Garde A M, eds., Zir- conium in the Nuclear Industry: 9th International Sympo- sium, ASTM STP 1132, Baltimore: ASTM International, 1991:643.
  • 4Pecheur D, Godlewski J, Peybern~s J, Fayette L, No~ M, Frichet A, Kerrec O. In: Sabol G P, Moan G D, eds., Zir- conium in the Nuclear Industry: 12th International Sym- posium, ASTM STP 1354, Philadelphia: ASTM Interna- tional. 2000:793.
  • 5Zhou B X, Li Q, Huang Q, Miao Z, Zhao W J, Li C. Nuc Power Eng, 2000; 21:43.
  • 6Sabol G P, Comstock R J, Weiner R A, Larouere P, Stanutz R N. In: Garde A M, Bradley E R, eds., Zirconium in the Nuclear Industry: l Oth International Symposium, ASTM STP 1245, Ann Arbor: ASTM International, 1994: 724.
  • 7Nikulina A V, Markelvo V A, Peregud M M, Bibilashvili Y K, Kotrekhov V A, Lositsky A F, Kuzmenko N V, Shevnin Y P, Shamardin V K, Kobylyansky G P, Novoselov A E. In: Bradley E R, Sabol G P, eds., Zirconium in the Nuclear In- dustry: 1 lth International Symposium, A STM STP 1295, Ann Arbor: ASTM International, 1996:785.
  • 8Zhao W J, Miao Z, Jiang H M, Yu X W, Li W J, Li C, Zhou B X. J Chin Soc Corros Prot, 2002; 22:124.
  • 9Li Z K, Liu J Z, Li P Z, Zhou L, Song Q Z. Rare Met Mater Eng, 1999; 28:101.
  • 10Li Z K, Liu J Z, Zhu M S, Song Q Z. Rare Met Mater Eng, 1996; 25:43.

共引文献125

同被引文献20

引证文献4

二级引证文献7

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