期刊文献+

第二相对Zr-4合金在400℃过热蒸汽中腐蚀吸氢行为的影响 被引量:17

Effect of the Second Phase Particles on the Hydrogen Absorption of Zircaloy-4 Alloy Corroded in Super-Heated Steam of 400℃
在线阅读 下载PDF
导出
摘要 采用不同的热处理方法制备了Zr(Fe,Cr)2第二相大小、多少及Fe/Cr比不同的样品,并研究了Zr(Fe,Cr)2第二相对Zr-4合金腐蚀时吸氢行为的影响。结果表明,不同热处理的Zr-4样品,经400℃/10.3MPa过热蒸汽腐蚀后吸氢量差别很大,与耐腐蚀性能之间并没有直接的对应关系。经β相加热空冷处理的样品第二相较小,也比较少,虽然耐腐蚀性能最差,但吸氢分数最低;经800℃加热处理的样品第二相粗大,数量增多,腐蚀速率略低于β相处理的样品,但吸氢分数最高;经720℃和600℃加热处理的样品第二相大小介于前2种样品之间,数量也很多,腐蚀速率明显低于β相处理的样品,但吸氢分数却高于后者。认为镶嵌在金属/氧化膜界面处还未被氧化的Zr(Fe,Cr)2第二相可以作为吸氢的优先通道,因而第二相的大小和数量是影响Zr-4合金腐蚀时吸氢行为差别的主要原因。 Zircaloy-4 specimens with different amounts, sizes and (Fe/Cr) ratios of the second phase Zr(Fe,Cr)2 particles have been prepared by different heat-treatments in order to further understanding the role of the second phase in hydrogen absorption which is investigated by corrosion tests in the super-heated steam of 400 ℃/10.3 MPa. Results show that the amount absorbing hydrogen is quite different with different heat-treatments, not proportional directly to the corrosion resistance. The β-treated specimen, in which the second phase Zr(Fe,Cr)2 particles are finer and less, shows the lowest hydrogen absorption fraction, although it has the highest corrosion rate. The specimens treated at 800 ℃, in which the the second phase particles are coarser and more, shows the highest hydrogen absorption fraction with corrosion rate only a little lower than that of β-treated specimen. The specimen treated at 720℃, in which the second phase particles are moderate in size but more in amount, shows a higher hydrogen absorption fraction than the β-treated specimen, but it has much lower corrosion rate than the specimens treated at 800 ℃. So, it is concluded that the amount and size of the second phase Zr(Fe,Cr)2 particles are responsible for different hydrogen absorption behaviors for different heat-treated specimens, as un-oxided second phase Zr(Fe,Cr)2 particles embedded and exposed at the metal/oxide interface could act as a perfect path for hydrogen absorption.
出处 《稀有金属材料与工程》 SCIE EI CAS CSCD 北大核心 2007年第11期1915-1919,共5页 Rare Metal Materials and Engineering
基金 国家自然科学基金资助项目(50371052) 上海市重点学科建设资助项目(T0101) 核燃料及材料国家级重点实验室资助项目(514810102.04.QT06.01)
关键词 锆-4合金 吸氢性能 耐腐蚀性能 热处理 Zr(Fe Cr)2第二相 Zircaloy-4 hydrogen absorption corrosion resistance heat treatments Zr(Fe,Cr)2
  • 相关文献

参考文献3

二级参考文献8

  • 1徐永波,金属学报,1979年,15卷,367页
  • 2IAEA-TECDOC-996, Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants[R]. IAEA. Vienna. 1998,ISSN 1011-4289, Jan, 1998.
  • 3Bryner J S. The Cyclic Nature of Corrosion of Zr-4 in 633K Water[J]. J Nucl Mater. 1979, 82: 84.
  • 4Hirsch P B, Howie A, Nicholson R Bet al. Electron Microscopy of Thin Crystals[M], London, Butterworths,1965, Chapter 15,353.
  • 5Zhou Bangxin. Electron Microscopy Study of Oxide Films Formed on Zircaloy-2 in Superheated Steam [C].in Van Swam L F P, Eucken C M, Eds. Zirconium in the Nuclear Industry: Eighth International Symposium,ASTM STP 1023, American Society for Testing and Materials, Philadephia, 1989, 360 - 373.
  • 6Cox B. Processes Occurring During the Breakdown of Oxide Films on Zirconium Alloys[J]. J Nucl Mat, 1969,29: 50.
  • 7周邦新,李强,黄强,苗志,赵文金,李聪.水化学对锆合金耐腐蚀性能影响的研究[J].核动力工程,2000,21(5):439-447. 被引量:40
  • 8周邦新,李强,姚美意,刘文庆.锆-4合金氧化膜中的晶粒形貌观察[J].稀有金属材料与工程,2003,32(6):417-419. 被引量:15

共引文献53

同被引文献155

引证文献17

二级引证文献80

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