原子能科学技术Issue(2)：271-276,6.DOI:10.7538/yzk.2014.48.02.0271
核电厂新型预应力混凝土安全壳及其非能动冷却系统设计与分析
Design and Analysis of New Prestressed Concrete Containment and Its Passive Cooling System for Nuclear Power Plants
谭效时 1李晓伟 1李笑天 1何树延1
作者信息
- 1. 清华大学 核能与新能源技术研究院，北京 100084
- 折叠
摘要
Abstract
A new nuclear power plant prestressed concrete containment and its passive cooling system design were proposed for CAP1700 nuclear power plant as an example . T he thermal-hydraulic calculation method for the new passive containment cooling sys-tem of CAP1700 was introduced and the operating parameters in accident condition were obtained .The result shows that the design of passive containment cooling system for CAP1700 is feasible and can meet the cooling demand in accident condition .Reservoir capacity of tank has a big margin and can be further optimized by calculation .关键词
非能动/热工水力/预应力混凝土安全壳Key words
passive/thermal-hydraulic/prestressed concrete containment分类
能源科技引用本文复制引用
谭效时,李晓伟,李笑天,何树延..核电厂新型预应力混凝土安全壳及其非能动冷却系统设计与分析[J].原子能科学技术,2014,(2):271-276,6.
