混合堆增殖钍基燃料组件中子学分析  

Neutronics Calculation of Fusion-Fission Hybrid Breeding Thorium Fuel Assembly

作　　者：马续波[1] 陈义学[1] 全国萍[1] 王悦[1] 韩静茹[1] 陆道纲[1] 

机构地区：[1]华北电力大学核科学与工程学院,北京102206

出　　处：《核动力工程》2012年第1期129-133,共5页Nuclear Power Engineering

基　　金：国家自然科学基金(10705011;10875042);中央高校基本科研业务费专项资金(09MG11);长江学者和创新团队发展计划(IRT0720);先进核燃料循环863项目(2009AA050701)

摘　　要：采用压水堆17×17燃料组件模型,用燃料组件参数计算程序DRAGON分别对混合堆增殖钍燃料组件和全铀组件的中子学特性进行了研究,分析组件的燃料温度系数、慢化剂温度系数及其与燃耗的关系。计算结果表明,混合堆增殖钍燃料组件和全铀组件的中子特性相似,但钍燃料组件中的乏燃料组件中的次锕系核素(MA)的含量明显减少。A preliminary comparative study of the physical properties among 17×17 fuel assembly in PWRs for prototype between uranium assembly and hybrid breeding thorium-based assembly has been investigated respectively using the DRAGON software.The parameters such as fuel temperature coefficient,moderator temperature coefficient and that variation as a function of operation period have been investigated.Results show that the neutron properties of uranium-based assembly and hybrid breeding thorium-based assembly are similitude,but MA mass of hybrid breeding thorium-based assembly is evidently less than those of the uranium assembly.

关 键 词：混合堆增殖钍基燃料 中子学 温度系数 

分 类 号：TL329[核科学技术—核技术及应用]