摘要
针对超临界水堆的能谱特性及钍燃料的中子特性,提出了一种应用于超临界水堆的新型铀钍混合燃料组件设计方案,并利用组件计算程序Dragon"对该设计在不同工况下的中子学特性进行了分析,包括:无限增殖因数、反应性温度系数、易裂变材料存量比(FIR)等,以及它们随燃耗变化的规律。另外,通过改变混合燃料组件中燃料棒的慢化剂-燃料比,探究了其对燃料组件中子学特性的影响。结果表明:超临界水堆较硬的中子能谱有利于产生易裂变核素,同时该新型燃料组件在提高燃料利用率和减少次锕系元素存量方面具有一定的优势。
A novel uranium-thorium mixed fuel assembly for SWCR is introduced in this paper, based on the neutron spectrum of SCWR and neutronic characteristics of thorium fuel. Neutronic characteristics of the introduced fuel assembly have been investigated using the Dragon codes. The parameters in different working conditions, such as infinite multiplication factors, reactivity temperature coefficients, fissile inventory ratio （FIR） and its relation with the operation period have been assessed by comparing with conventional uranium assembly. Moreover, the Moderator-to-Fuel Ratio （MFR） was changed in order to investigate its influence on the neutronic characteristics of fuel assembly. Results show that the harder neutron spectrum of SCWR is favorable forbreeding the fissile nuclides, and the new uranium-thorium mixed fuel assembly has advantages on both efficient fuel utilization and lower minor actinide generation.
出处
《核科学与工程》
CSCD
北大核心
2015年第3期546-554,共9页
Nuclear Science and Engineering
基金
中山大学"百人计划"引进人才科研启动经费(45000-3210001)
中央高校基本科研业务费专项资金(11lgpy90)
教育部"新世纪优秀人才支持计划"(NCET-10-0846)
广东省科技项目(2014A010106012)
关键词
超临界水堆
钍燃料
中子学
supercritical water cooled reactor
thorium fuel
neutronics
