首页 | 本学科首页   官方微博 | 高级检索  
     

长寿命小型自然循环铅基快堆燃料选型
引用本文:刘紫静,赵鹏程,任广益,柯国土,于涛,谢金森,陈珍平,何丽华,谢芹,曾浩. 长寿命小型自然循环铅基快堆燃料选型[J]. 原子能科学技术, 2020, 54(5): 944-953. DOI: 10.7538/yzk.2019.youxian.0402
作者姓名:刘紫静  赵鹏程  任广益  柯国土  于涛  谢金森  陈珍平  何丽华  谢芹  曾浩
作者单位:南华大学 核科学技术学院,湖南 衡阳421001;中国原子能科学研究院,北京102413;南华大学 核燃料循环技术与装备湖南省协同创新中心,湖南 衡阳421001;生态环境部 核与辐射安全中心,北京100082
摘    要:针对铅基快堆长寿命、小型化、自然循环的设计目标,构建铅基快堆堆芯模型并开展燃料选型研究,选取U-Pu、Th-U循环燃料及氧化物、氮化物、碳化物、金属燃料,分析比较了不同燃料的物性参数、在不同能谱条件下的堆芯物理特性。结果表明:在偏软能谱中,Th基燃料堆芯增殖能力更强,反应性系数负值更大,热工安全裕量更大、裂变产物容留能力更强;PuN-ThN燃料堆芯燃耗特性最佳,可在较疏松栅格条件下获得较强增殖能力,减少燃料装载量,确保固有安全性,兼顾堆芯长寿命、小型化、自然循环设计要求;但堆芯有效缓发中子份额较小,不利于反应性控制。

关 键 词:铅基快堆   燃料选型   物理特性   增殖特性

Fuel Selection of Long Life Small Natural Circulation Lead-based Fast Reactor
LIU Zijing,ZHAO Pengcheng,REN Guangyi,KE Guotu,YU Tao,XIE Jinsen,CHEN Zhenping,HE Lihua,XIE Qin,ZENG Hao. Fuel Selection of Long Life Small Natural Circulation Lead-based Fast Reactor[J]. Atomic Energy Science and Technology, 2020, 54(5): 944-953. DOI: 10.7538/yzk.2019.youxian.0402
Authors:LIU Zijing  ZHAO Pengcheng  REN Guangyi  KE Guotu  YU Tao  XIE Jinsen  CHEN Zhenping  HE Lihua  XIE Qin  ZENG Hao
Affiliation:College of Nuclear Science and Technology, University of South China, Hengyang 421001, China; China Institute of Atomic Energy, Beijing 102413, China;Cooperative Innovation Center for Nuclear Fuel Cycle Technology and Equipment, University of South China, Hengyang 421001, China; Nuclear and Radiation Safety Center, Ministry of Ecology and Environment, Beijing 100082, China
Abstract:Aiming at design goals for long life, miniaturization and natural circulation of lead-based fast reactors, a lead-based fast reactor core model was constructed and fuel selection was carried out. U-Pu and Th-U cycle fuels, oxides, nitrides, carbides and metal fuels were selected to be researched, and the physical parameters of different fuels, the physical characteristics of cores under different energy spectra were analyzed and compared. The results show that in the soft energy spectrum, Th-based fuel core has the larger breeding ratio, and the larger negative reactivity coefficient, the larger thermal safety margin and the stronger fission product retention capacity. PuN-ThN fuel core has the best burnup characteristics, can obtain the higher breeding ratio under loose grid conditions, reduce fuel load, ensure inherent safety, and meet the design requirements of long core life, miniaturization and natural circulation; however, the effective delayed neutron fraction of the core is small, which is not conducive to reactivity control.
Keywords:lead-based fast reactor  fuel selection  physical property  breeding characteristic  
点击此处可从《原子能科学技术》浏览原始摘要信息
点击此处可从《原子能科学技术》下载全文
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号