摘要
为深入研究第四代核能系统堆型之一铅基快堆的物理性能,进一步提高模块化铅基快堆的安全性和经济性,对铀锆合金燃料装载的不同功率水平的模块化铅基快堆堆芯特性进行研究,发现当堆芯功率提升至一定水平时,堆芯的增殖优势在规定寿期内不能得到充分释放。基于此现象,对模块化铅基快堆铀锆合金燃料堆芯的概念设计进行优化,基于堆芯功率水平和寿期,选择合适的栅距棒径比和燃料芯体有效密度,通过调整单位体积内的铀装量和235U装量调整堆芯的增殖性能,最终使堆芯反应性变化与堆芯功率、寿期基本匹配,寿期内堆芯反应性几乎不发生变化。优化后降低了堆芯反应性控制难度,充分利用了堆芯的增殖性能,同时合理的栅距棒径比为堆芯热工分析提供了安全和设计裕量,有效提高了堆芯的经济性和安全性。
In order to deeply study the physical properties of lead-based fast reactor,one of the reactor types of the fourth generation nuclear energy system,and further improve the safety and economy of modular lead-based fast reactor,the core characteristics of modular lead-based fast reactor with different power levels loaded with uranium-zirconium alloy fuel were studied,and it was found that when the core power was raised to a certain level,the breeding advantage of the core could not be fully released within the specified life.Based on this phenomenon,the conceptual design of modular lead-based fast reactor uranium-zirconium alloy fuel core is optimized.Based on the core power level and service life,the appropriate ratio of grid spacing to rod diameter and the effective density of fuel core are selected,and the breeding performance of core is adjusted by adjusting the uranium loading per unit volume and the 235U loading.Finally,the core reactivity changes are basically matched with the core power and service life,so that the core reactivity hardly changes during the service life.The optimization not only reduces the difficulty of core reactivity control,but also makes full use of the breeding performance of the core.At the same time,the reasonable ratio of grid spacing to rod diameter provides safety and design margin for thermal analysis of the core,which effectively improves the economy and safety of the core.
作者
娄磊
王连杰
陈长
赵晨
周冰燕
严明宇
马党伟
Lou Lei;Wang Lianjie;Chen Chang;Zhao Chen;Zhou Bingyan;Yan Mingyu;Ma Dangwei(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2023年第6期1-8,共8页
Nuclear Power Engineering
关键词
铅基
铀锆合金
增殖
燃料芯体密度
栅距棒径比
Lead-based
Uranium-zirconium alloy
Breading
Density of fuel core
Ratio of grid spacing to rod diameter
