摘要
以COBRA-Ⅳ和NLSANMT程序为基础,开发了堆芯三维物理-热工耦合程序C4/NK。针对两个典型的反应性引入事故(RIA),即NEACRP弹棒基准题和提棒基准题,分别进行了验证计算。与参考值和其他程序的计算结果相比,C4/NK耦合程序具有较好的精度,能正确模拟瞬态过程中的物理-热工反馈现象。
Based on sub-channel code COBRA-Ⅳand neutron kinetics code NLSANMT, a three dimensional neutronics and thermal-hydraulic coupled code C4/NK was developed.In order to verify the coupled code,two typical reactivity initiated accidents （RIA）：NEACRP control rod ejection benchmark and uncontrolled rods withdrawal benchmark at zero power,were calculated.The comparison of results with the reference solutions and other coupled codes shows that the C4/NK code has good accuracy and can correctly simulate the neutronics and thermal-hydraulic feedback phenomena during the transient.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2010年第11期1328-1334,共7页
Atomic Energy Science and Technology
关键词
三维物理-热工耦合
C4/NK程序
弹棒基准题
提棒基准题
three dimensional neutronics and thermal-hydraulic coupling
C4/NK code
control rod ejection benchmark
uncontrolled rods withdrawal benchmark
