[1]谢岱良,李鸿飞,李上元,等.压水堆核电厂安全壳贯穿件老化管理[J].大众科技,2019,21(07):34-37.
　Aging Management of Containment Penetrations in Pressurized WaterReactor(PWR ) Nuclear Power Plant[J].Popular Science & Technology,2019,21(07):34-37.
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压水堆核电厂安全壳贯穿件老化管理()
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《大众科技》[ISSN:1008-1151/CN:45-1235/N]

卷:
21
期数:
2019年07
页码:
34-37
栏目:
电力与机械
出版日期:
2019-07-20

文章信息/Info

Title:
Aging Management of Containment Penetrations in Pressurized WaterReactor(PWR ) Nuclear Power Plant
作者:
谢岱良;  李鸿飞;  李上元;  王志敏
（广西防城港核电有限公司，广西 防城港 538001）
关键词:
压水堆; 核电厂; 安全壳贯穿件; 老化管理
Keywords:
PWR;  nuclear power plant;  containment penetration;  aging management
文献标志码:
A
摘要:
压水堆核电厂安全壳贯穿件是安全壳内外流体输送、设备或人员进出、电缆穿行等工作的关键部件，文章对贯穿件结构和材料进行阐述，从老化管理角度对压水堆核电厂安全壳贯穿件老化机理进行分析，包括腐蚀、疲劳、机械磨损，并开展基于戴明循环（ PDCA ）的管理，在对安全壳贯穿件老化机理充分认知的基础上提出管理策略。
Abstract:
The containment penetration of pressurized water reactor (PWR) nuclear power plant is the key component of fluidtransportation inside and outside the containment, equipment or personnel entering and leaving, cable traversing and so on. The structureand material of penetration are described. The aging mechanism of PWR nuclear power plant containment penetration is analyzed fromthe perspective of aging management, including corrosion, fatigue and machinery. The management based on Deming Cycle(PDCA) wascarried out, and the management strategies were put forward on the basis of fully understanding the aging mechanism of containmentpenetrating parts.

参考文献/References:

[1] 林诚格,郁祖盛,欧阳予.非能动安全先进压水堆核电技术[M].北京:原子能出版社,2010.[2] 高飞,周宇,殷静华,等.核电厂安全壳老化防护监测的设计[J].腐蚀与防护,2011,32(12):988-990.[3] Mcginty T J.Stell containment degradation and associatedlicense renewal aging management issues[R].NRCInformation Notice 2010, Washington DC:NRC,2011:1-6.[4] Mcginty,Tracy G.Containment liner corrosion[R].NRCInformation Notice 2010.Washington DC:NRC,2010:1-5.[5] Jordan E L.Degraded coatings and corrosion of stellcontainment vessels[R].NRC Information Notice 1989.Washington DC:NRC,1989:1-2.[6] Grimes B K.Unexpected opening of both doors in an airlock[R].NRC Information Notice 1993.Washington DC:NRC,1993:1-3.[7] 杨林,王永焕,林松涛.核电厂安全壳老化管理[J].工业建筑,2009(S1):1094-1097.[8] ASME BPVC Section III-2013 Rules for construction ofnuclear facility components[S].New York:ASME,2013.

备注/Memo

备注/Memo:
【收稿日期】 2019-05-13【作者简介】谢岱良（ 1983 －），男，广西防城港核电有限公司工程师，从事性能试验及技术管理方面的研究。
更新日期/Last Update: 2020-01-22