摘要
AP1000核电厂以非能动技术而成为第三代核电厂的典型代表。本文主要介绍AP1000核电厂的非能动系统，并从概率风险评价（PRA）的角度，通过纵向和横向的对比，分析了非能动技术应用对AP1000核电厂的堆芯损伤频率（CDF）和大量放射性释放频率（LRF）的影响。
AP1000 nuclear power plant is a typical third generation plant with passive technique application in the design. This paper briefly describes the passive systems in AP1000 and comes to a conclusion of the influence of passive technique application on core damage frequency （CDF） and large release frequency （LRF） by comparing PRA results of various nuclear power plants.
出处
《核电工程与技术》
2008年第1期11-14,共4页
Nuclear Power Engineering and Technology
