摘要
开发了三维物理与热工-水力耦合的PWR堆芯瞬态分析程序NGFMN-K/COBRA-Ⅳ/COBRA-Ⅳ(NCC)。少群时空中子动力学计算采用格林函数节块法程序NGFMN-K,隐式耦合子通道程序COBRA-Ⅳ实现瞬态计算。采用P10H8B功率重构方法给出热组件栅元功率分布,耦合另一个COBRA-Ⅳ程序模块,进行热组件子通道分析得到安全参数。对NEACRP-L-335C1弹棒基准问题的计算表明,NCC程序的计算结果与参考结果符合很好,说明程序计算正确,可用于评估事故结果。
A coupled three-dimensional neutronics and thermal-hydraulics code NGFMN- K/COBRA-IV/COBRA-IV (NCC) was developed for PWR core transient analysis. The neutronics model was the NGFMN K code based on nodal Green's function method. One COBRA-IV sub-channel code was coupled with NGFMN-K implicitly for core transient calculation. Through integrating the other COBRA-N code for sub-channel calculation on hot assemble, the code system was capable of evaluating safety-related parameters. The pin power distribution in hot assemble was constructed by P10H8B pin power reconstruction method. Numerical evaluation results on the NEACRP-L-335 C1 rod ejection benchmark problem show that the calculation results of NCC code agree well with reference solutions. NCC is capable of accident analysis.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2013年第2期266-270,共5页
Atomic Energy Science and Technology
关键词
时空动力学
格林函数节块法
热工一水力
功率重构
安全参数
spatial kinetics
nodal Green's function method
thermal-hydraulics
powerreconstruction
sa{ety parameter