摘要
从现有水冷反应堆核电厂存在堆芯熔化危险这一安全问题的焦点出发,分析了改进型反应堆AP-600、SIR、非能动安全反应堆PIUS和具有固有安全的模块高温气冷堆MHTGR等的安全特性.按照下一代水冷反应堆的设计要求和用户要求,提出了解决水堆核电厂安全问题的新概念——自安全铀氢锆反应堆,该堆型可能成为世界水堆核电发展的一个方问。中国核动力研究设计院正在探讨这种堆型。
Based on the safety problems that the current water cooled reactor nuclear power plants have the potential danger of core melt, the paper comments upon the safety behaviors of the advanced reactors (AP-600, SIR) and passive safety reactors (PIUS, MHTGR). According to design and user's requirements for next generation water cooled reactor, the paper put forward a new concept about self safety U-ZrH reactor(SUR) which is able to solve the safety problems for water cooled reactor nuclear power plant and become a development direction for world water cooled reactor nuclear power plants. This type of reactor is researchedin NPIC.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1991年第4期1-8,共8页
Nuclear Power Engineering
