研究论文

反应堆停冷系统阀门接管失效分析

  • 王斐 ,
  • 朱伟 ,
  • 温榜 ,
  • 蒋国富 ,
  • 唐洪奎 ,
  • 尹春艳 ,
  • 彭艳华 ,
  • 任亮
展开
  • 中国核动力研究设计院, 成都 610041
王斐,助理研究员,研究方向为核材料辐照效应,电子信箱:reshiwangfei@163.com

收稿日期: 2015-05-08

  修回日期: 2015-11-27

  网络出版日期: 2016-03-25

Failure analysis for valve nozzle of shutdown cooling system in reactor

  • WANG Fei ,
  • ZHU Wei ,
  • WEN Bang ,
  • JIANG Guofu ,
  • TANG Hongkui ,
  • YIN Chunyan ,
  • PENG Yanhua ,
  • REN Liang
Expand
  • Nuclear Power Institute of China, Chengdu 610041, China

Received date: 2015-05-08

  Revised date: 2015-11-27

  Online published: 2016-03-25

摘要

反应堆检修过程中发现停冷系统的阀门接管出现裂纹,裂纹出现在焊缝坡口部位,为分析裂纹产生的原因,需对阀门接管进行失效分析。采用目视检测和渗透检测方法,对裂纹出现的区域进行无损检查,确定了裂纹的数量和方向。根据无损检查结果对典型裂纹区域进行了显微分析和成分分析。检查结果表明,裂纹从管壁内侧向外侧扩展,裂纹周围晶粒未发现变形痕迹,裂纹区域与非裂纹区域晶粒未发现区别;裂纹横断面呈现脆性断裂特征,裂纹内部发生了腐蚀,腐蚀产物的主要成分为氧;结合阀门接管的运行工况分析认为,该阀门接管失效原因为应力腐蚀。

本文引用格式

王斐 , 朱伟 , 温榜 , 蒋国富 , 唐洪奎 , 尹春艳 , 彭艳华 , 任亮 . 反应堆停冷系统阀门接管失效分析[J]. 科技导报, 2016 , 34(5) : 93 -96 . DOI: 10.3981/j.issn.1000-7857.2016.05.012

Abstract

Cracks found in the weld groove parts of valve nozzle of the shutdown cooling system of a reactor in repairing is analyzed. The reasons of the cracks, the crack number and orientations are confirmed by visual inspection and penetranting testing. According to the results of nondestructive inspection, typical cracks regions are cut into some samples including crack transect samples,longitudinal crack samples and transverse crack samples. Scanning electron microscopy is used to investigate the microstructure and micro zone composition of the crack transect. Optical microscopy is used to analyze the microstructures of the longitudinal crack and the transverse crack. The results show that cracks may extend from the inside to outside wall and that grain deformation around the crack is not found. There are no obvious grain differences between crack and non-crack regions. Brittle fracture characteristic exists in crack cross section, and the internal corrosion of crack is found. The main component of corrosion products is oxygen, and the corrosion is caused by oxidation of stainless steel. Combined with the valve nozzle operating conditions, the reason for the failure of valve nozzle is believed to be stress corrosion cracking.

参考文献

[1] 庄毅, 黄兴蓉, 姜百华, 等. CARR应急堆芯冷却系统停堆冷却措施分析[J]. 核动力工程, 2006, 27(5):79-83. Zhuang Yi, Huang Xingrong, Jiang Baihua, et al. Analysis of cooling measures for ECCS at CARR shutdown[J]. Nuclear Power Engineering, 2006, 27(5):79-83.
[2] 孙丙新, 尹毅, 陆波, 等. 4号炉主蒸汽管道排空气管孔裂纹的原因分析及处理[J]. 内蒙古电力技术, 2004, 22(1):17-18. Sun Bingxin, Yin Yi, Lu Bo, Zhou Yan. Cause analysis and treatment on craze of ventilation pipe's hole of main steam pipes for No.4 boiler[J]. Inner Mongolia Electric Power, 2004, 22(1):17-18.
[3] 李中伟, 张东文, 赵纪峰, 等. 600 MW机组高温再热蒸汽管道放气管裂纹原因分析与处理[J]. 热加工工艺, 2010, 39(1):157-159. Li Zhongwei, Zhang Dongwen, Zhao Jifeng, et al. Cause analysis and settlement of exhaust pipes crack in high temperature reheated steam pipe of 600 MW unit[J]. Hot Working Technology, 2010, 39(1):157-159.
[4] 李中伟, 冯砚厅, 张东文, 等. 300 MW锅炉再热出口管道焊缝开裂原因分析[J]. 热加工工艺, 2011, 40(19):196-197. Li Zhongwei, Feng Yanting, Zhang Dongwen, et al. Analysis on welding seam crack of 300 MW boiler reheater output pipes[J]. Hot Working Technology, 2011, 40(19):196-197.
[5] 邱宏斌. 奥氏体不锈钢输油管道焊缝的应力腐蚀失效分析[J]. 化工设备与管道, 2011, 48(4):68-72. Qiu Hongbin. Stress corrosion failure analysis for weld in austenitic steel piping for oil transportation[J]. Process Equipment & Piping, 2011, 48(4):68-72.
[6] 刘瑞堂, 刘文博, 刘锦云. 工程材料力学性能[M]. 哈尔滨:哈尔滨工业大学出版社, 2001:114-117. Liu Ruitang, Liu Wenbo, Liu Jinyun. Mechanical properties of engineer-ing materials[M]. Harbin:Harbin Institute of Technology Press, 2001:114-117.
[7] 苗中辉, 焦增庚, 蔡琦. 0Cr18Ni10Ti管道腐蚀失效模式诊断不确定推理研究[J]. 核动力工程, 2007, 28(3):78-81. Miao Zhonghui, Jiao Zenggeng, Cai Qi. Uncertainty reasoning of mode diagnosis for 0Cr18Ni10Ti pipe corrosion failure[J]. Nuclear Power Engi-neering, 2007, 28(3):78-81.
[8] 贺彩红, 王世宏. 不锈钢的腐蚀种类及影响因素[J]. 当代化工, 2006, 35(1):40-42. He Caihong, Wang Shihong. Corrosion type and influence factor of stainless steel[J]. Contemporary Chemical Industry, 2006, 35(1):40-42.
[9] 顾宝珊, 纪晓春, 刘建华. 奥氏体不锈钢的应力腐蚀开裂[J]. 石油化工腐蚀与防护, 2005, 22(6):41-44. Gu Baoshan, Ji Xiaochun, Liu Jianhua. Stress corrosion cracking of aus-tenitic steel[J]. Corrosion & Protection in Petrochemical Industry, 2005, 22(6):41-44.
[10] 奚明华, 张静江. 316不锈钢应力腐蚀断裂扫描电镜研究[J]. 理化检验:物理分册, 1999, 35(4):155-157. Xi Minghua, Zhang Jingjiang. SEM Study on stress corrosion cracking of 316 stainless steel[J]. Physical Testing and Chemical Analysis:Physical Testing, 1999, 35(4):155-157.
[11] 粱汉生, 蒋定功, 张朝文, 等. 阀门组件老化敏感点预警值的确定及老化缓解对策[J]. 核动力工程, 2005, 26(6):97-102. Liang Hansheng, Jiang Dinggong, Zhang Chaowen, et al. Establish-ment of alarm value for aging susceptibility point of valve subassem-bly and countermeasures for aging mitigation[J]. Nuclear Power Engi-neering, 2005, 26(6):97-102.
[12] 曹雪明, 李世伟, 薛飞. 秦山核电厂死管段筛选及管理对策[J]. 核动力工程, 2013, 34(6):148-152. Cao Xueming, Li Shiwei, Xue Fei. Screening and management of Dead-end pipe in Qinshan NPP[J]. Nuclear Power Engineering, 2013, 34(6):148-152.
[13] 刘金华, 文燕, 张雪梅, 等. 反应堆压力容器密封面材料非正常工况下的腐蚀性能研究[J]. 核动力工程, 2012, 33(1):83-87. Liu Jinhua, Wen Yan, Zhang Xuemei, et al. Corrosion properties of sealing surface material for RPV under abnormal working conditions[J]. Nuclear Power Engineering, 2012, 33(1):83-87.
文章导航

/