节点文献

研究堆稳压器隔离及卸压方案仿真研究

Study on Isolation and Depressurization Scheme for Pressurizer of Research Reactor

  • 推荐 CAJ下载
  • PDF下载
  • 不支持迅雷等下载工具,请取消加速工具后下载。

【作者】 曾畅赖建永余小权苏荣福唐辉

【Author】 Zeng Chang;Lai Jianyong;Yu Xiaoquan;Su Rongfu;Tang Hui;Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China;

【机构】 中国核动力研究设计院核反应堆系统设计技术重点实验室

【摘要】 建立了某气体稳压型研究堆在失水事故(LOCA)下局部破口及整体系统的数值仿真模型。针对主管道破口进行数值分析,研究系统流量、压力和破口流量的关系,获得破口的特性参数。通过在系统仿真模型中耦合破口特性参数,对隔离及卸压2种事故下防止稳压器上部气体进入反应堆的应对方案进行了研究。结果表明,破口截面的流量主要取决于系统的压力,采用卸压方案要优于隔离方案。

【Abstract】 The numerical simulation models of local break and the entire system under loss of coolant accident(LOCA) for a certain gas pressurized research reactor are established. Based on the simulation of main pipe break, the relations among system flowrate, system pressure and break flowrate are studied, and the resistance characteristics of the break is obtained. Coupled the characteristic data with the system simulation model, the two schemes, isolation and depressurization, to prevent the gas into the reactor under LOCA accident are studied. The results show that, the break flowrate mainly depends on the system pressure, and the depressurization scheme is better than the isolation scheme.

  • 【文献出处】 核动力工程 ,Nuclear Power Engineering , 编辑部邮箱 ,2015年S2期
  • 【分类号】TL411
  • 【下载频次】52
节点文献中: 

本文链接的文献网络图示:

本文的引文网络