第三代压水堆核电站CAP14001E级壳内电缆附件研制及鉴定试验  被引量:1

Qualification Test&Development of Class 1E In Containment Cable Accessories for the Third-generation PWR Nuclear Power Plant CAP1400

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作  者:王庆玖 张军[2] 严振杰 吕波 WANG Qingjiu;ZHANG Jun;YAN Zhenjie;LYU Bo(Jiangsu Huakan Nuclear Power Equipment Technology Co.,Ltd.,Changzhou of Jiangsu Prov.213011,China;Shanghai Jiao Tong University,Shanghai 200240,China;State NuclearPower Engineering Company,Shanghai 200233,China;Institute of Plasma Physics Chinese Academy of Sciences,Hefei of Anhui Prov.230031,China)

机构地区:[1]江苏华侃核电器材科技有限公司,江苏常州213011 [2]上海交通大学,上海200240 [3]国核工程有限公司,上海200233 [4]中国科学院等离子体物理研究所,安徽合肥230031

出  处:《核科学与工程》2020年第2期179-188,共10页Nuclear Science and Engineering

基  金:国家科技重大专项-大型先进压水堆及高温气冷堆核电站(核电站主要辅助设备自主设计与制造技术研究)(2014ZX06004004-007)。

摘  要:CAP1400是经过国际原子能机构的反应堆安全评审,达到国际安全法规最新要求的先进非能动核电技术。CAP14001E级壳内电缆附件是连接核岛安全壳内贯穿件和电缆、电缆和电缆以及电缆和其他电气设备的关键部件,对其在核电站运行期间的服役性能有很高的要求。本文详述了CAP14001E级壳内电缆附件的技术要求、材料研究、结构设计、研制及鉴定试验过程,首次在国内完成了该系列产品的试制及鉴定试验,为未来该系列电缆附件应用于第三代压水堆核电站CAP1400壳内打下了基础。The license for CAP1400 nuclear reactor has been approved by National Nuclear Safety Administration of China,and the reactor design has successfully passed the International Atomic Energy Agency s Generic Reactor Safety Review(GRSR).The CAP1400 class 1E in containment cable accessories are key components for connecting the penetrators and cables,cables and cables,as well as cables and other electrical equipments within the nuclear island.In this article,the technical requirements,material research,structural design,development and identification test process of CAP14001E class in containment cable accessories are described in detail,the trial production and qualification test of this series of products was completed in China for the first time,which lays a foundation for the future application of cable accessories in CAP1400 containment of the Generation III PWR nuclear power plant.

关 键 词:CAP14001E级壳内电缆附件 技术要求 材料研究 结构设计 鉴定试验 

分 类 号:TM623[电气工程—电力系统及自动化]

 

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