超临界水堆堆芯新型燃料组件设计分析  

Design analysis of a new SCWR fuel assembly using a coupled method

作　　者：刘晓晶[1] 杨婷[1] 程旭[1] 

机构地区：[1]上海交通大学核科学与工程学院,上海200240

出　　处：《核科学与工程》2011年第1期22-27,共6页Nuclear Science and Engineering

基　　金："973计划"项目资助(No.2007CB209804)

摘　　要：超临界水堆(SCWR)作为六种第四代未来堆型中唯一的水冷反应堆,具有良好的经济性与技术延续性。本文采用最新开发的热工-物理耦合计算程序对超临界水堆方形燃料组件进行稳态热工与中子物理耦合分析,提出一种新型的超临界水堆堆芯燃料组件设计。现有单排组件设计与新型双排燃料组件设计的计算结果表明,双排组件具有功率径向分布均匀,包壳温度峰值小,慢化剂温度较低等优点。Among the six GEN-Ⅳ reactor concepts recommended by the Gen-Ⅳ International Forum（GIF）,supercritical water-cooled reactor（SCWR） is the only reactor type with water as coolant.Compared to the existing reactors,it has economic advantage and technology continuity.Based on the newly developed coupling code,analysis on the square SCWR assembly is carried out in this paper.A new design concept of SCWR fuel assembly is proposed.The results achieved so far indicate favorable thermal-hydraulic performance and neutron-physical behavior of the new fuel assembly compared to the previous ones.

关 键 词：超临界水冷堆(SCWR) 耦合分析 燃料组件设计 

分 类 号：TL32[核科学技术—核技术及应用]