期刊文献+

Inconel690在ETA/NH_3水化学环境中的均匀腐蚀行为研究 被引量:8

Study on General Corrosion Behaviors of Inconel690 in Simulation Environment with ETA/NH_3
下载PDF
导出
摘要 本文在模拟压水堆二回路的高温高压水化学环境下,研究了蒸汽发生器传热管材料镍基合金Inconel690试样在乙醇胺(ETA)和氨(NH3)水化学环境中的均匀腐蚀行为。结果显示:在5 000h均匀腐蚀试验后,ETA水化学环境下试样的均匀腐蚀速率为0.21mg/(m2·h),NH3水化学环境下试样的均匀腐蚀速率为0.50mg/(m2·h);在ETA水化学环境下试样表面形成的氧化膜中铬含量更高,氧化膜的保护性更好。以上结果表明,Inconel690在ETA水化学环境下的耐蚀性强于NH3水化学环境。 The general corrosion behaviors of Inconel690 for steam generator (SG) tube were studied in the simulation environment of secondary loop of pressurized water reac‐tor (PWR) with ethanolamine (ETA) and ammonia (NH3 ) separately .After exposed to the simulation environment with ETA for 5 000 hours , the weight loss rate of Inconel690 is 0.21 mg/(m2·h) .But for the tests under the NH3 environment after 5 000 hours ,the weight loss rate of Inconel690 is 0.50 mg/(m2·h) .In addition ,there is more chromium in the oxidation film formed in the simulation environment with ETA ,and the oxidation film is more protective .The results show that Inconel690 is more resistant to general corrosion in the environment with ETA than that in the envi‐ronment with NH3 .
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2015年第3期518-522,共5页 Atomic Energy Science and Technology
基金 国家科技重大专项资助项目(2011ZX06004-017)
关键词 压水堆 Inconel690 均匀腐蚀 乙醇胺 PWR Inconel690 general corrosion ethanolamine
  • 相关文献

参考文献4

二级参考文献16

  • 1杨武 顾睿祥.金属的局部腐蚀[M].北京:化学工业出版社,1995.75-84. 被引量:60
  • 2候保荣.海洋腐蚀环境理论及其应用[M].北京:北京科学出版社,1999.199-260. 被引量:1
  • 3郭锦保.化学海洋学[M].厦门:厦门大学出版社,1997.. 被引量:1
  • 4国家标准局.金属材料在表面海水中常规暴露腐蚀试验方法[M].,1986.. 被引量:1
  • 5EPRI. Advanced Light Water Reactor, Utility Requirements Document, Volume I, Palo Alto, CA, 1990, (EPRI publication). 被引量:1
  • 6EPRI. Advanced Light Water Reactor, Utility Requirements Document, Volume III, ALWR Passive Plant. Revision 7, 12/1995, (EPRI publication). 被引量:1
  • 7IAEA. Objectives for the Development of Advanced Nuclear Plants, IAEA-TECDOC-682. Vienna. 1993. 被引量:1
  • 8DOE. A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010. Volume Ⅱ, Main Report (internal), 31/10/2001. 被引量:1
  • 9DOE Nuclear Energy Research Advisory Committee and Generation IV Intl Forum. A Technology Roadmap for Generation IV Nuclear Energy Systems, GIF002-00, 12/2002. 被引量:1
  • 10Cummins W E, et al. Schulz. Westinghouse AP1000 Advanced Passive Plant. Symposium. Paper 3235, ICAPP03, Cordoba, Spain, May 4-7, 2003. 被引量:1

共引文献62

同被引文献85

引证文献8

二级引证文献12

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