原子能科学技术2017，Vol.51Issue(1)：84-88,5.DOI:10.7538/yzk.2017.51.01.0084
余热排出系统安全壳外破口事故源项分析
Accident Source Term Analysis of Residual Heat Removal System Break outside Containment
刘建昌 1沈永刚 1陶俊1
作者信息
- 1. 中广核研究院有限公司，广东深圳 518035
- 折叠
摘要
Abstract
When the inlet pipe of the residual heat removal (RHR) system ruptures on the dow nstream of the containment isolation valve , the radionuclides in the primary coolant release to the atmosphere directly .A method to assess the radiological conse‐quence of this accident was given in this paper according to the accident process .In addi‐tion ,calculation results were given with different assumptions of the isolation time of the broken RHR system .The results show that 300 s can be chosen as the limiting time ,as one of the design basis of the RHR isolation system for Chinese generation Ⅲnuclear power plant , according to the calculation results and the requirement of GB 6249—2011 .关键词
余热排出系统/事故源项/分析方法Key words
residual heat removal system/accident source term/analysis method分类
能源科技引用本文复制引用
刘建昌,沈永刚,陶俊..余热排出系统安全壳外破口事故源项分析[J].原子能科学技术,2017,51(1):84-88,5.
