CANDU堆内钍-铀增殖循环初步研究  

Research on Thorium-Uranium Breeding Recycle Roadmap in CANDU

作　　者：施建锋[1] 毕光文[1] 杨波[1] 

机构地区：[1]上海核工程研究设计院,上海200233

出　　处：《核电工程与技术》2012年第2期1-4,27,共5页Nuclear Power Engineering and Technology

摘　　要：本文首先从中子动力学理论出发，给出了在CANDU堆内实现钍一铀增殖循环的基本条件。随后，分析了不同的初始^233U含量和不同的功率水平下，反应性和易裂变核素含量随燃耗的变化过程。初始瑚U的获取则使用了直接自身再循环的方法。基于以上分析和结果。本文最后给出了CANDU堆内实现钍一铀增殖循环的技术路线。该技术路线是后续重水堆钍一铀循环研究工作的重要基础。Breeding constraints of Thorium-Uranium fuel cycle in CANDU were unfolded based on neutronics theory for CANFLEX bundles loaded with homogeneous （233U, Th）O2 fuel. Performances of reac- tivity change and fissile nuclides accumulation during burnup were analyzed for different initial 233U weight percent and different power densities. In order to obtain the preliminary 2z3U in （2z3U, Th）O2 fuel, the direct self-recycle method was used for heterogeneous CANFLEX bundles. Based on the above-mentioned anal- ysis and results, a roadmap for Thorium-Uranium breeding recycle in CANDU reactors was proposed. This roadmap is a necessary precondition for the subsequent work on Thorium-Uranium Recycle in CANDU.

关 键 词：钍-铀燃料循环 增殖循环 CANDU 

分 类 号：TM623[电气工程—电力系统及自动化]