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非对称预紧载荷下核反应承压容器密封性能分析方法研究

熊光明 段远刚 邓小云 刘攀

压力容器2017,Vol.34Issue(12):27-31,54,6.
压力容器2017,Vol.34Issue(12):27-31,54,6.DOI:10.3969/j.issn.1001-4837.2017.12.005

非对称预紧载荷下核反应承压容器密封性能分析方法研究

Sealing Behavior Analysis Method of Reactor Pressure Vessel under Asymmetric Preload

熊光明 1段远刚 2邓小云 1刘攀2

作者信息

  • 1. 深圳中广核工程设计有限公司,广东深圳518172
  • 2. 核电安全监控技术与装备国家重点实验室,广东深圳518172
  • 折叠

摘要

Abstract

For the reactor pressure vessel (RPV) threaded hole damage analysis of sealing performance,a finite element model containing three bolts and surrounding structure was built,compared with which was a 180 degree model.Based on the models,the sealing performance under the asymmetric preload was studied.The key indicators are deduced,include vertical displacement,horizontal displacement,bolt loads,etc.It shows that both models can verify the performance of the seal structure,which used to evaluate the reliability of the RPV sealing structure,and is the basis to solve the sealing problem of main bolt damage cases.

关键词

非对称预紧/核反应承压容器/螺孔损伤/密封研究

Key words

asymmetric preload/reactor pressure vessel(RPV)/injured threaded holes/seal research

分类

机械制造

引用本文复制引用

熊光明,段远刚,邓小云,刘攀..非对称预紧载荷下核反应承压容器密封性能分析方法研究[J].压力容器,2017,34(12):27-31,54,6.

基金项目

中国广核集团尖峰计划项目(K-A2013.061) (K-A2013.061)

压力容器

OA北大核心CSTPCD

1001-4837

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