使用大亚湾核电站乏燃料的池式堆概念核设计

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Nuclear Conceptual Design of Spent Fuel Pool Reactor Loaded With Spent Fuels of Daya Bay Nuclear Power Station

1. Department of Engineering Physics,Tsinghua University,Beijing 100084,China; 2. Technical Center,China Guangdong Nuclear Power Holding Co. Ltd.,Shenzhen,518124,China

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。
- 乏燃料池式堆 /
- 循环长度 /
- 水铀比 /
- 乏燃料冷却时间
Abstract: 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.
- Spent fuel pool reactor /
- Cycle length /
- Water-uranium ratio /
- Spent fuel storage time