200MW核供热堆的固有安全性  

The Inherent Safety Features of 200MW Nuclear Heating Reactor

作　　者：张作义[1] 高祖瑛[1] 王彦生[1] 李金才[1] 

机构地区：[1]清华大学核能所,北京100084

出　　处：《核动力工程》1993年第3期227-231,255,共6页Nuclear Power Engineering

摘　　要：本文分析了200MW核供热堆冷却剂大量丧失的严重事故。事故分析表明:反应堆在发生失水事故时,其动态过程进展缓慢,借助于慢化剂反应性反馈而安全地自动停堆,堆芯始终被水淹没,使得反应堆具有很好的固有安全性。反应堆在失去全部热阱的51.6小时后,堆芯顶部开始裸露,该事故发生频率低于10^(-12)/堆·年。All accidents of LOCA for 200MW Nuclear Heating Reactor are analyzed in this paper. The analyzed results show that: The event sequences develop slowly, and the reactor will automatically shutdown by means of the nuclear reactivity beedback of the moderator density. The reactor core are always covered with water. 200MW Nuclear Heating Reactor is of very good inherent safety. In the event of loss of all heat sink, after 51.6 hours, the top of reactor core will be uncovered with water, its frequency is less than 10^(-12)/reactor·year.

关 键 词：供热堆 固有安全性 事故分析 安全 

分 类 号：TL413.2[核科学技术—核技术及应用]