摘要
计算了使用大亚湾核电站乏燃料的池式堆所需的组件数,分析了135Xe,149Sm和241Pu对反应性的影响及乏燃料冷却时间与循环长度的关系,指出抽掉含钆棒能够增加循环长度。设计了使用大亚湾核电站乏燃料的池式堆堆芯布置方案。从核设计的角度进一步阐明了这种堆型的可实现性。
This work calculates the required assembly number of spent fuel pool reactor loaded with spent fuels of Daya Bay Nuclear Power Station, and analyses the influence of Xe-135, Sm-149 and Pu-241 on reactivity and the relationships between cycle length and spent fuel storage time. A way of prolonging cycle length by drawing all gadolinium rods is also given, and then a core layout is designed. Nuclear analysis of this layout further shows that this type of reactor is realizable.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2004年第5期385-389,共5页
Nuclear Power Engineering
关键词
乏燃料池式堆
循环长度
水铀比
乏燃料冷却时间
Calculations
Control rods
Gadolinium
Radioactive waste storage
Reactivity (nuclear)
Spent fuels
