基于FLUENT软件耦合点堆中子动力学模型的行波堆热工水力分析  

Thermal-hydraulics analysis in traveling-wave reactor based on FLUENT software coupling with point reactor kinetic model

作　　者：黄思洋[1] 张大林[1] 丛腾龙 苏光辉[1] 

机构地区：[1]西安交通大学核科学与技术学院,西安7100492

出　　处：《中国科技论文》2015年第11期1253-1257,共5页China Sciencepaper

基　　金：国家自然科学基金资助项目(11105103);高等学校博士学科点专项科研基金资助项目(20110201120046)

摘　　要：行波堆是一种能够实现自持增殖和燃耗革新概念的先进反应堆系统。根据泰拉能源公司最新设计的钠冷行波堆泰拉能源一号的具体参数,建立泰拉能源一号1/6堆芯物理模型,利用FLUENT软件的用户接口(UDF/UDS),开发点堆中子动力模型的计算程序和模块,用于计算堆芯的功率;利用FLUENT软件中的多孔介质模型模拟堆芯三维流场;再将两者耦合起来进行计算,研究行波堆的物理热工耦合和安全特性。进行稳态运行工况计算和反应性引入事故瞬态计算,计算结果表明:稳态的计算结果与设计值吻合得比较好;根据瞬态计算结果,在设计的反应性引入事故瞬态工况下,如果不启用停堆保护系统,泰拉能源一号也是安全的。Traveling-wave reactor （TWR） is an advanced reactor system of innovative concept which can achieve self-sustaining propagation and burn-up. This study establishes one-sixth model of the whole reactor core based on the specific parameters of so- dium cooled TWR TP-1 which is the latest design of the Terra Power Energy Company. The program module of the point reactor kinetic model is developed to calculate the core power by using FLUENT user interface （UDF/UDS）. The three-dimensional flow field of the reactor core is simulated with the porous media model. Coupling the above two, the characteristics of the neutronics and thermal-hydraulics coupling and safety in TWR are investigated. Two operation conditions are calculated： one steady condi- tion and one transient condition, i.e. reactivity-insertion accident. The calculation results of the steady condition show good agreement with TP-1 design values. In the reactivity-insertion accident, if the shutdown protection system is not running, TP-1 would be safe.

关 键 词：核动力工程技术 行波堆 FLUENT数值模拟 多孔介质 点堆中子动力学 

分 类 号：TL33[核科学技术—核技术及应用]