摘要
本文介绍了供热堆反应性温度系数的计算方法,以200MW堆为设计实例,计算了初装堆芯的燃料温度系数和慢化剂温度系数。同时,对于首炉运行工况下的温度系数作了比较细致的计算,这些计算结果为低温堆物理设计提供了科学依据。
The calculating method of temperature coefficient of reactivity for NHRs ispresented in this paper. An example case has been made for 200MW heating reactor.The fuel and moderator temperature coefficients were calculated for initial -- loaded coreand for the first cycle. The results provide a basis for the reactor safety analysis.
出处
《清华大学学报(自然科学版)》
EI
CAS
CSCD
北大核心
1994年第3期88-93,共6页
Journal of Tsinghua University(Science and Technology)
基金
国家"八五"攻关项目
关键词
温度系统
有效倍增因子
供热堆
temperature coefficient
effective multiplication factor
nuclear heating