耦合的PWR三维物理与热工-水力堆芯瞬态分析程序系统NLSANMT/COBRA-Ⅳ  

Coupled Kinetic and Thermal-hydraulic Three Dimensional Code System NLSANMT/COBRA-Ⅳ for PWR Core Transient Analysis

作　　者：廖承奎[1] 谢仲生[2] 

机构地区：[1]上海核工程研究设计院,上海200233 [2]西安交通大学核能系,西安710049

出　　处：《核动力工程》2003年第5期412-416,共5页Nuclear Power Engineering

摘　　要：介绍了采用非线性迭代半解析节块展开法求解的三维节块时-空中子动力学计算程序NLSANMT,并将其与子通道热工-水力堆芯分析程序COBRA-Ⅳ耦合,形成PWR三维物理与热工-水力堆芯瞬态分析程序系统NLSANMT/COBRA-Ⅳ。对OECD NEACPR PWR弹棒基准问题的计算表明,即使每个组件使用一个节块、每个节块一个通道,NLSANMT/COBRA-Ⅳ的计算结果仍然和参考值符合得很好。In this paper a three dimensional neutron kinetic nodal code NLSANMT has been developed based on the nonlinear iteration semi-analytical nodal expansion method, and coupled with the sub-channel thermal-hydraulic core analysis code COBRA-Ⅳ to form the integrated code system NLSANMT/COBRA-Ⅳ for PWR core transient analysis. The application of this coupled code system to the OECD NEACRP PWR hot zero power full core rod ejection benchmark problem shows that good agreement with the reference solu-tion is obtained, even when one node per assembly and one channel per assembly are used.

关 键 词：时-空中子动力学 节块法 热工水力 

分 类 号：TL329.2[核科学技术—核技术及应用]