原子能科学技术Issue(2)：277-284,8.DOI:10.7538/yzk.2014.48.02.0277
大功率先进压水堆压力容器外部冷却能力研究
Study on External Reactor Vessel Cooling Capacity for Advanced Large Size PWR
金頔 1李飞 2刘晓晶 1程旭1
作者信息
- 1. 上海交通大学 核科学与工程学院，上海 200240
- 2. 国核 北京 科学技术研究院有限公司，北京 100029
- 折叠
摘要
Abstract
External reactor vessel cooling (ERVC ) is widely adopted as a part of in-vessel retention (IVR) in severe accident management strategies .In this paper ,some flow parameters and boundary conditions , eg ., inlet and outlet area , water inlet temperature ,heating power of the lower head ,the annular gap size at the position of the lower head and flooding water level ,were considered to qualitatively study the effect of them on natural circulation capacity of the external reactor vessel cooling for an advanced large size PWR by using RELAP5 code .And the calculation results provide some basis of analysis for the structure design and the following transient response behavior of the system .关键词
大功率先进压水堆/压力容器外部冷却/自然循环能力Key words
advanced large size PWR/external reactor vessel cooling/natural circulation capacity分类
能源科技引用本文复制引用
金頔,李飞,刘晓晶,程旭..大功率先进压水堆压力容器外部冷却能力研究[J].原子能科学技术,2014,(2):277-284,8.
