刘贺同,高齐乐,党俊杰.ACP1000堆型RVD系统中不同核安全级别管道的应力分析与评定[J].装备环境工程,2019,16(2):54-59. LIU He-tong,GAO Qi-le,DANG Jun-jie.Stress Analyzing and Evaluating of Different Rank Pipes of RVD System of ACP1000 Reactor[J].Equipment Environmental Engineering,2019,16(2):54-59.
ACP1000堆型RVD系统中不同核安全级别管道的应力分析与评定
Stress Analyzing and Evaluating of Different Rank Pipes of RVD System of ACP1000 Reactor
  修订日期:2019-02-25
DOI:10.7643/ issn.1672-9242.2019.02.011
中文关键词:  ACP1000堆型  柔性系数  RVD系统  应力分析与评定
英文关键词:ACP1000 reactor  flexibility coefficient  RVD system  stress analyzing and evaluating
基金项目:
作者单位
刘贺同 中国核电工程有限公司,北京 100840 
高齐乐 中国核电工程有限公司,北京 100840 
党俊杰 中国核电工程有限公司,北京 100840 
AuthorInstitution
LIU He-tong China Nuclear Power Engineering Co., Ltd, Beijing 100840 
GAO Qi-le China Nuclear Power Engineering Co., Ltd, Beijing 100840 
DANG Jun-jie China Nuclear Power Engineering Co., Ltd, Beijing 100840 
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中文摘要:
      目的 保证RVD系统管道的应力评定能够满足RCCM规范要求,保证RVD系统能够正常运行。方法 首先探究弯头的柔性系数对不同核安全级别管道在应力计算上的影响;其次,借助管道分析软件PIPESTRESS对RVD管道系统最初版本的布置设计进行分析与评定,并分析应力过大的原因。考虑到柔性系数的影响,对不同核安全级别管道布置采取不同的调整方法,降低管道在各个工况下的应力。结果 经过修改后的RVD系统管道应力满足RCCM规范要求。结论 通过对RVD系统管道的应力的分析与评定,掌握了此类问题的解决方法,总结了设计中应注意的问题,为核电站中的管道设计提供参考。
英文摘要:
      Objective To ensure that stress analyzing and evaluating of the RVD system could meet requirements of RCCM code and the RVD system could run properly. Methods Firstly, the effect of flexibility coefficient on evaluating different rank pipes of the model in different codes was analyzed. Then with the help of PIPSTRESS software, the first version of piping layout for the RVD piping system was analyzed and evaluated, and the causes of excessively high stress were analyzed. Considering the effect of flexibility coefficient, different adjustment methods was applied to different rank pipes, the stress of each loading case was depressed. Results The modified RVD piping system satisfied the RCCM code. Conclusion By analyzing and evaluating the RVD piping system, the way for solving similar problems was achieved; and the problems of the design of the piping system was summarized, which can be a guidance of piping system design of nuclear power plant.
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