核电厂主回路耦合分支管道的地震分析研究
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摘要
核电厂反应堆主冷却剂回路连接众多的分支管道,根据分支管道连接的支撑系统,可分为直接和间接与主管道相连两大类。对于直接与主管道相连的分支管道,业界已建立较成熟的解耦准则,但对于间接与主管道连接的分支管道,解耦问题并未形成准则。为了获得主回路分析模型的边界条件,确保反应堆冷却剂回路抗震分析的准确性,进行蒸发器分支管标高和管径对主回路地震分析影响的评估,得到对实际工程有参考意义的结论,同时为其他间接与主管道相连的大型支管解耦论证提供参考,最终为此类支管解耦准则的确立打下基础。
A large number of branch pipes are connected to the Reactor Coolant Loop(RCL) of nuclear power station. According to the support system connected by the branch pipelines, it can be divided into two categories: direct and indirect connected to the RCL. For the branch pipelines directly connected to the RCL, the industry has established more mature decoupling criteria. However, for the branch pipelines that are indirectly connected to the RCL, the decoupling criteria have not been formed. In order to obtain the boundary conditions of the RCL analysis model and ensure the accuracy the seismic analysis of the RCL, carries out the influence of the elevation and diameter of the branch pipe line on the seismic analysis of the RCL, and obtains the conclusions that have reference significance for the actual project. At the same time, provides reference for other large-scale branch pipelines influence demonstrations that are indirectly connected to RCL, and finally lays a foundation for the establishment of such branch pipeline decoupling criteria.
A large number of branch pipes are connected to the Reactor Coolant Loop(RCL) of nuclear power station. According to the support system connected by the branch pipelines, it can be divided into two categories: direct and indirect connected to the RCL. For the branch pipelines directly connected to the RCL, the industry has established more mature decoupling criteria. However, for the branch pipelines that are indirectly connected to the RCL, the decoupling criteria have not been formed. In order to obtain the boundary conditions of the RCL analysis model and ensure the accuracy the seismic analysis of the RCL, carries out the influence of the elevation and diameter of the branch pipe line on the seismic analysis of the RCL, and obtains the conclusions that have reference significance for the actual project. At the same time, provides reference for other large-scale branch pipelines influence demonstrations that are indirectly connected to RCL, and finally lays a foundation for the establishment of such branch pipeline decoupling criteria.
引文
[1]U.S.Nuclear Regulatory Commission.Standard Review Plan,-3.7.2.Seismic System Analysis Rev.2,1989.
[2]王晓雯,夏祖讽.核电站反应堆厂房结构与主回路系统耦联模型的抗震分析[J].第11届全国反应堆结构力学会议论文集
[3]陈星文.反应堆冷却剂回路抗震分析技术及敏感性研究[J].第18届全国反应堆结构力学会议论文集.
[4]朱宝,何树延,张征明.HTR-10主回路压力边界三壳整体抗震分析[J].第10届全国反应堆结构力学会议论文集.
[2]王晓雯,夏祖讽.核电站反应堆厂房结构与主回路系统耦联模型的抗震分析[J].第11届全国反应堆结构力学会议论文集
[3]陈星文.反应堆冷却剂回路抗震分析技术及敏感性研究[J].第18届全国反应堆结构力学会议论文集.
[4]朱宝,何树延,张征明.HTR-10主回路压力边界三壳整体抗震分析[J].第10届全国反应堆结构力学会议论文集.