期刊文献+

锆材管件的失效分析 被引量:1

Failure Analysis of Zirconium Pipes
下载PDF
导出
摘要 某化工企业装置中,其锆材(Zr702)管件在生产过程和停车检修时均发现裂纹,并且裂纹已经贯穿管壁。根据对出现裂纹的管件进行断口分析和能谱分析可知,锆管的开裂是沿晶开裂。引起锆管开裂的因素包括力学因素、焊接因素以及温度、介质因素等。 In the chemical device of a plant, cracks of zirconium (Zr702) pipes are found during production process and shutdown for maintenance, and the cracks have been run through the tube wall. According to the fracture analysis and spectrum analysis of the pipes with cracks, the cracks are intergranular cracks. Factors causing cracks include mechanical factors, welding factors as well as temperature and medium factors.
作者 蒋爱国
出处 《化工装备技术》 CAS 2013年第3期42-44,共3页 Chemical Equipment Technology
关键词 锆管件 裂纹 失效分析 冷压成形 焊接 Zirconium pipe Crack Failure analysis Cold briquetting Welding
  • 相关文献

参考文献3

二级参考文献18

  • 1Daniel Cubicciotti, Stanley M Howard, Robin L Jones. the formation of iodine - Induced stress corrosion cracking in zircaloys[J] .Journal of Nuclear Materials, 1978, 78:2.?A
  • 2P S Sidky. Iodine stress corrosion cracking of zircaloy reactor cladding: Iodine chemistry ( A Review ) [J]. Journal of nuclear materials, 1998, 256:1.?A
  • 3Tsing- Tyan YANG, Chuen - Horng Tsai. On the susceptibility to stress corrosion cracking of zircaloy in an iodine containing enviroment [J]. Journal of Nuclear Materials. 1989,166:252.?A
  • 4Woo Seog Ryu, Young Hwan Kang, Jai - Young Lee. Effects of iodine concentration on iodine - induced stress corrosion cracking of zircaloy - 4 tube[J]. Journal of Nuclear Materials,1988,152:194.?A
  • 5Kee - Nam Choo, Su -Ⅱ Pyun, Jong - Kyo Choi. A study on the mechanism of iodine- induced stress corrosion cracking of zircaloy- 4[J]. Journal of Nuclear Materials, 1987, 149:289.?A
  • 6M Fregonese, Florence Lefebvre, Clement Lemaignan, et al.Influence of recoil - implanted and thermally released iodine on Ⅰ - SCC of zircaloy - 4 in PCI - conditions: Chemical aspects[J].Journal of Nuclear Materials, 1999, 265:245.?A
  • 7P Hofmann, J Spino. Stress corrosion cracking of zircaloy- 4cladding at elevated temperatures and its relevance to transient LWR fuel rod behaviour [J]. Journal of Nuclear Materials,1984, 125: 85.?A
  • 8Patrick Jacques, Florence Lefebvre, Clement Lemaignan. Deformation - corrosion interactions for Zr alloys during Ⅰ - SCC crack initiation Part Ⅰ: Chemical contributions [J]. Journal of Nuclear Materials, 1999, 264: 239.?A?A
  • 9IAEA-TECDOC-996, Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants[R]. IAEA. Vienna. 1998,ISSN 1011-4289, Jan, 1998.
  • 10Bryner J S. The Cyclic Nature of Corrosion of Zr-4 in 633K Water[J]. J Nucl Mater. 1979, 82: 84.

共引文献55

同被引文献2

引证文献1

二级引证文献1

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