期刊文献+

核电汽轮机防应力腐蚀裂纹技术 被引量:11

Technology of Stress Corrosion Cracking Resistance in Nuclear Steam Turbines
在线阅读 下载PDF
导出
摘要 我国将陆续开工建设一批CPR、AP1000和EPR等堆型的百万等级核电站,而核电汽轮机主要部件工作在湿蒸汽环境下,防止这些部件产生应力腐蚀裂纹甚至导致最终断裂是汽轮机的关键设计。本文介绍了应力腐蚀的机理,并说明了汽轮机部件应力腐蚀的3个重要影响因素:材料的屈服强度、工作应力水平和工作环境,从可能产生应力腐蚀部位的应力限制和对应力腐蚀裂纹增长的控制方面,提出如何从设计上防止这些部件因为应力腐蚀而失效的措施,这些措施有效性已经在国外的核电站运行中得到了验证,为叶轮、叶片、汽缸等关键部件长期安全运行提供可靠的技术保证。 An amount of CPR,AP1000 and EPR type/'s nuclear power plants are to be built in China.As the principal components of nuclear steam turbine working in saturated steam conditions,it is essential for turbine design to avoid initiation and growth of stress corrosion cracking(SCC) which may finally lead to components/'rupture.This article introduces the mechanism of stress corrosion,indicates three factors influencing the SCC behavior-yield strength of material,working stress and environment.Through limiting the working stress of SCC possible position and controlling the SCC growth,the design measures how to avoid components failure due to SCC are put forward.Having been validated in oversea nuclear power plants operation,these measures can supply technical guarantees for key components such as disc,blade and cylinder.
作者 蒋浦宁
出处 《热力透平》 2010年第2期89-92,96,共5页 Thermal Turbine
关键词 核电汽轮机 湿蒸汽环境 应力腐蚀裂纹 裂纹扩展速度 屈服强度 应力强度因子 nuclear steam turbine saturated steam conditions stress corrosion cracking(SCC) crack growth rate yield strength stress intensity factor
  • 相关文献

参考文献18

  • 1D Rosario,P Riccardella,S Tang.Development of an LP Rotor Rim-Attachment Cracking Life Assessment Code(LPRimLife)[R].EPRI-TR-110407,1999.
  • 2G Engelhardt,D Macdonald.Corrosion of Low Pressure Steam Turbine Components[R].EPRI-100557,2000.
  • 3G Engelhardt,D Macdonald,A Davydov.Development of Model to Predict Stress Corrosion Cracking and Corrosion Fatigue of Low Pressure Turbine Components[R].EPRI-1012204,2007.
  • 4G Engelhardt,D Macdonald.Development of Code to Predict Stress Corrosion Fatigue of Low Pressure Turbine Components[R].EPRI-1004190,2004.
  • 5G Engelhardt,D Macdonald.Development of Code to Predict Stress Corrosion Fatigue of Low Pressure Turbine Components[R].EPRI-1009690,2005.
  • 6G Engelhardt,D Macdonald,A Davydov.Development of Code to Predict Stress Corrosion Cracking and Corrosion Fatigue of Low Pressure Turbine Components[R].EPRI-1010184,2005.
  • 7P K Nair,F F Lyle,J E Buckingham,H G Pennick.Guidelines for Predicting the Life of Steam Turbine Disks Exhibiting Stress Corrosion Cracking[R].EPRI-NP-6444,1989.
  • 8Oliver Mandement.Nuclear Steam Turbine Retrofit:The "CP1" Example[C].Financial Performance Enhancements at Operating Nuclear Power Plants,2003:pp65-66.
  • 9D A Rosario,R Viswanathan,C H Wells,G J Licina.Stress Corrosion Cracking of Steam Turbine Rotors[J].CORROSION,1998,54(7):P531-545.
  • 10M W Smiarowski,R H Menning,V B Tolentino,L J Curran.Turbine Modernization Projects at Susquehanna and Salem Nuclear Plants Maximize Performance at Current and Future Uprate Steam Condition[C].POWER-GEN International 2006-Orlando,FL.2006.

同被引文献73

引证文献11

二级引证文献16

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