管道流体加速腐蚀(Flow Accelerated Corrosion)是核电厂和常规电厂碳钢或低合金钢材料汽水管道的一个重要的老化机理,历史上曾发生过美国萨里核电站2号机组和日本美滨核电站3号机组管道破裂等导致人员伤亡的严重事故;本文简要总结了核电厂管道流体加速腐蚀的经验教训、机理及其老化管理的一些方法和对策.
参考文献
[1] | Bindi Chexal et al.EPRI TR-106611-R1 flow-accelerated corrosion in power plants[R].United States Electric Power Research Institute,1998. |
[2] | Sweeney T J.A review of the virginia power erosion/corrosion inspection program[A].San Diego California,1991 |
[3] | James G Partlow .NRC generic letter 89-08 erosion/corrosion-induced pipe wall thinning[R].United States Nuclear Regulatory Commission,1989. |
[4] | Division of regulatory improvement programs.NUREG-1801 generic aging lessons learned (GALL) report[R].United States Nuclear Regulatory Commission,2001. |
[5] | NISA's interim report into mihama-3 accident[R].Japan Citizens Nuclear Information Center,2004. |
[6] | Robert L Tapping.Flow-accelerated corrosion[A].,2005 |
[7] | Smith C L et al.NUREG/CR-5632 incorporating aging effects into probabilistic risk assessment-a feasibility study utilizing reliability physics models[R].United States Nuclear Regulatory Commission,2001. |
上一张
下一张
上一张
下一张
计量
- 下载量()
- 访问量()
文章评分
- 您的评分:
-
10%
-
20%
-
30%
-
40%
-
50%