期刊文献+

压水堆核电机组二回路给水系统弯头减薄原因分析

Cause Analysis for Elbow Thinning of the Secondary Loop Feedwater System in PWR NPP
下载PDF
导出
摘要 2012年3月,某核电厂大修期间对二回路部分管线进行了现场壁厚测量,发现电动主给水泵系统弯头存在壁厚减薄现象。文章对其中的一根弯头在实验室进行了失效分析。利用超声波测厚仪在实验室对换下的弯头进行壁厚测厚并利用等离子光谱发生仪等设备及分析手段对异常减薄部位和减薄一般部位进行了分析研究。结果表明管壁异常减薄是由于流动加速腐蚀(FAC)引起的。最后,根据分析结果,结合国内外的最新研究进展,对管道的管理及变更提出了建议。 Wall thickness of some secondary system pipelines were measured on site during the refueling outages in March 2012. Wall thinning happened in some components of APA system. This paper focused on the cause analysis of an elbow with that phenomenon. Wall thickness was carefully measured in laboratory using ultrasonic thickness meter and found that wall thinning happened nearly all elbows including two abnormal thinning regions. Analytical research was conducted using ICP, stereo microscope, SEM ,XRD, ANSYS. The result shows that the cause of wall thinning is flow accelerated corrosion. Based on the analysis result and international research progress, this paper makes some suggestions to avoid and alleviate FAC in the secondary system.
出处 《中国核电》 2013年第2期177-181,共5页 China Nuclear Power
关键词 二回路管线 壁厚减薄 流动加速腐蚀 pipelines of the secondary system, wall thinning, flow accelerated corrosion
  • 相关文献

参考文献6

  • 1NISArs Interim Report Into Mihama 3 Accident [Z]. Japan Citizens Nuclear Information Center, 2004.
  • 2束国刚,薛飞,遆文新,汪小龙,陆念文,刘鹏,戴忠华.核电厂管道的流体加速腐蚀及其老化管理[J].腐蚀与防护,2006,27(2):72-76. 被引量:49
  • 3Masanori Naitoh,陈耀东,Shunsuke Uchida,Hidetoshi Okada.流动加速腐蚀引起的管壁减薄分析及验证[J].金属学报,2011,47(7):784-789. 被引量:17
  • 4Naitoh M, Uchida S, Koshizuka S, Ninokata H, Hiranuma N, Dosaki K, Nishida K, Akiyama M, Saitoh H. J Nucl Sci Technol, 2008, 45 : 1116.
  • 5Uchida S, Naitoh M, Uehara Y, Okada H, Hiranuma N, Sugino W, Koshizuka S. J Nucl Sci Technol, 2008, 45. 1275.
  • 6Uchida S, Naitoh M, Uehara Y, Okada H, Hiranuma N, Sugino W, Koshizuka S. J Nucl Sci Technol, 2009, 46:31.

二级参考文献26

  • 1Nuclear and Industrial Safcty Agency. Secondary Piping Rupture Accident at Mihama Power Station, Unit 3 of the Kansai Electric Power Co., Inc. (Final report), Rev.1, Nu- clear and Industrial Safety Agency: Tokyo, Japan, 2005: 1.
  • 2Czajkowski C Z. Metallurgical Evaluation of an I8 inch Feedwater Line Failure at the Surry Unit 2 Power Station, NUREG/CR-4868, BNL-NUREG-52057, Brookhaven National Laboratory, 1987:1.
  • 3Uchida S, Naitoh M, Uehara Y, Okada H, Hiranuma N, Sugino W, Koshizuka S. Power Plant Chem, 2008; 11-12: 704.
  • 4Naitoh M, Uchida S, Koshizuka S Ninokata H, Hiranuma N, Dosaki K, Nishida K, Akiyama M, Saitoh H. J Nucl Sci Technol, 2008; 45:1116.
  • 5Uchida S, Naitoh M, Uehara Y, Okada H, Hiranuma N, Sugino W, Koshizuka S. J Nucl Sci Technol, 2008: 45: 1275.
  • 6Uchida S, Naitoh M, Uehara Y, Okada H, Hiranuma N, Sugino W, Koshizuka S, Lister D H. J Nucl Sci Technol, 2009; 46:31.
  • 7Uchida S, Naito M, Uehara Y, Okada H, Koshizuka S, Lis-ter D H. Proc 14th Int Conf Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, VA, Virginia Beach: ANS, 2009:973.
  • 8Uchida S, Naitoh M, Uehara Y, Okada H, Ohira T, Takiguchi H, Sugino W, Koshizuka S. J Nucl Sci Tech- nol, 2010; 47:184.
  • 9Naitoh M, Uchida S, Uehara Y, Okada H~ Koshizuka S. Proc ASME PVP2010, Bellevue, YVA, USA, July 18 22, Paper PVP2010-25517, 2010:887.
  • 10Tsuruta T, Murata K, Shoda Y, Yamamoto K. Proc Fontevraud 6 Contribution of Material Investigation to Improve the Safety and Performance of LWRs, Vol.1, ses- sion A, Fontevraud, France: French Nuclear Energy Soci- ety, 2006:181.

共引文献62

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